ML20107D256

Monthly Operating Rept for Jan 1985

ML20107D256
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/31/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85052, NUDOCS 8502220289
Download: ML20107D256 (9)

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PUBLIC SERVICE COMPANY OF COLORADO i

FORT ST. VRAIN NUCLEAR GENERATING STATION

.(3 MONTHLY OPERATIONS REPORT NO. 132 January, 1985 i

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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 January, 1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor was depressurized for the month, and decay heat removal was being performed by "1B" Helium Circulator and the Loop I Steam Generator. Helium Circulator "1A" was removed and shipped to San Diego to repair an interspace bearing water leak.

The circulator has not been returned due to problems noted during reassembly. The problems are being thoroughly analyzed and repaired. The arrival date for the circulator has not been determined.

The Loop II cold reheat Marmor. flanges have all been replaced with spoolpieces. The remaining work on the Loop II reheat flanges is to seal weld the upper Marmon flanges. This will start after the flange plugs are machined.

The circulating water tower has been isolated and drained to prevent icing, due to the low heat load during the present plant shutdown conditions. The Steam Jet Air Ejector (SJAE) has been isolated, and has been checked for proper jet size and water

(< leaks.

A concentrated effort was made to analyze System 21, Helium Circulator Bearing Water Pump problems. Pump, P-2101, was repaired and carefully analyzed to try to determine the causes of our recent bearing water pump problems. Initial indications were that the base was not level and that piping induced stresses on the pump during operation. The pump was returned to service on January 31, 1985. Vibration was approximately one mil, and the pump had a small leak. The pump and motor were shutdown, decoupled, the leak was fixed, and the pump was -

returned to service. The results of this rebuild will be t evaluated after the pump has operated for some time. When the l . pump was returned to service, Helium Circulator "1B" tripped due to air accumulation in the pump and lines. The circulator was I restarted with no complications. Later, another restart of P-2101 caused another helium circulator trip.

The refueling floor has been cleared of all items not required for the control rod drive rework program. The temporary ten ton crane has been installed. The refueling floor and hot service facility are being modified with special equipment items necessary to implement the control rod drive refurbishment program. This program is scheduled to last approximately two j months.

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(f The Essential Bus 480V Breakers were all checked for their annual inspection. Setpoint problems were noted on the first breaker tested, but no other breakers have shown a setpoint drift. This activity is essentially complete.

"1B" Instrument Air Compressor five year preventive maintenance inspection and overhaul has been completed and the compressor has been tested, passed, and returned to service. Operational problems developed and the compressor had to be shutdown for valve replacment. The compressor is now out of service.

A major leak occured on "A" Condensate Pump. That leak has been repaired. However, when trying to establish pump clearance, several condensate valves where found to be leaking, and are now being repaired.

Primary coolant circulation was terminated on January 21, 1985, to repair the leaking condensate header valves. All but one

, valve was returned to service on January 26, 1985. Helium Circulator "1B" was restarted for primary coolant circulation.

No secondary coolant was established. This arrangement is

, maintaining primary coolant temperatures between 170 and 4

200 degrees Fahrenheit. Secondary coolant will be established after the remaining valve is completed, and before the control

. rods are removed from the core, if necessary.

(?. . . . 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached i ~- .

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• Ie:ue 2 Docuzr no. 50-267

. orrums un mzron 1 .

ur: February 5, 1985 carm n Frank Novachek mzrnon (303) 785-2224 orrum: $*A".US so m

1. mit me : Fort St. Vrain - .

2. a.portins reriod: 850101 through 850131

3. ueensed thermal re er osit): 842

4. Nam. plate Rating (cross We): 342

5. Design Elsetrical Bating (met We): 330

6. nam == Dependable capacity (cross Isle): 342

7. me- Dependable caputty out m.): 330

8. If changes occur in capacity Raciass (1tems Neber 3 Through 7) Sinee last Report, cive Baesons:

None

9. roar in=1 To mich nastricted, If any (mt me): 280

10. asesons for ametrictions, is any: Per commitment to the NRC, long term operation above 85% power is oending completion of 8-0 startuo testing.

This Month Year to Date Ca mlative

u. noun in n.porties vert d 744 744 49,009 0.0 0.0 27,151.4 ,"

12. nam ar of moon n=etor ses critical

13. ne eter n ee m shutdown no.n 0.0 0.0 0.0 0.0 0.0 18,468.0

14. noun con rator on-um.

15. Unit n = ern shutdown 30 n 0.0 0.0 0.0 0.0 0.0 9,861,714.4

11. cross Thermal zo rar comerated osa)

17. cros Elaetrical znergy cenerated osm) 0 0 3,248,594

! Is. me nectrical zmesy cement.d osm) -2,017 -2,017 2,925,941

{ 0.0 0.0 37.7

19. Unit S'ervice rector

20. twit avanability r.eter 0.0 0.0 37.7

21. oute cap. city rutor (m ins noe m t> 0.0 0.0 18.1

22. m.tt capacity ru tor (m ins DER m t) 0.0 0.0 18.1

23. mit Forced outage mate 100.0 100.0 47.9 f 24. Shutdowns Schet.uled over Next 6 haths-(Type. Date, and Duration of zach): 850201 through

.3 E 331. 1.416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br />, Control Rod Drive Refurbishment.

850401 =

25. If shut Down at and of amport Period, zstimated Date or startup:

! 26. ' Units In Test Status (Prior to concretal operation):.

Forecast A:hieved mnAL cuncau:Y N/A N/A m m t zLze m c m N/A N/A comzacut orzamos N/A N/A L._

m Attechmant-3A AVERAGE DAILY UNIT POWER LEVEL 100 2 p g Docket No. 50-267 11 nit Fort St. Vrain #1 Date February 5, 1985_

Completed By Frank Novachek Telephone (303) 785-2224 math January, 1985 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 0.0 17 0.0 l 2 '0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 l

l 7 0.0 23 0.0 8 00 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 l

12 0.0 28 0. 0 '

13 .' O.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

.* Generator on line but no net generation.

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REFUELING INFORMATION I I l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l 1 l l 2. Scheduled date for next l 4th Refueling: l l refueling shutdown. l February 1, 1986 l l 1 l l 3. Scheduled date for restart l May 1, 1936 l l following refueling.  ! l l l l l 4. Will refueling or resumption oft No l l operation thereafter require a 1 - l

l. technical specification change l l l or other license amendment? l l l l l l If answer is yes, what, in l ---------------- l l . general, will these be? I l 1 - l l l If answer is no, has the reload l l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l No l l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? l l l l l l If no such review has taken l 1985 l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action l ---------------- l l and supporting information. l l l l 1 l 6. Important licensing considera- l l l tions associated with refuel- l l l ing, e.g., new or different l l l . fuel design or supplier, unre- l ---------------- l l viewed design or performance l l 1 analysis methods, significant l l l ' changes in fuel design, new l l l cperating procedures. l l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in ths-l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 143 spent fuel elements l n ,,- - yy- 4 - , g - -,--

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2 REFUELING INFORMATION (CONTINUED) l I l l 8. The present licensed spent fuell l l pool storage capacity and the l l l size of any increase in l Capacity is limited in size to l l licensed storage capacity that l about one-third of core l l has been requested or is l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. 1 l l .l l l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueling that can ce dis- l and DE-SC07-791001370 between l j charged to the spent fuel pool l Public Service Company of l

l. assuming the present licensed l Colorado, and General Atomic l .

l caoacity. I Comoany, and DOE.* l The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE at the _ Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

I Public Service company 2 Odlmdro

. 16805 WCR 19 1/2, Platteville, Colorado 80651 February 14, 1985 Fort St. Vrain Unit #1 P-85052 Office of Inspection and Enforcemect ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington. D.C. 20555 Docket No. 50-267

REFERENCE:

Facility Operating License No. DPR-34

SUBJECT:

Monthly Operations Report-January, 1985

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of January, 1985.

Sincerely, J. . Gahm Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm l

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