ML20112J414

Revised Monthly Operating Rept for Nov 1984

ML20112J414
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1984
From:	Novachek F PUBLIC SERVICE CO. OF COLORADO
To:
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ML20112J386	List: ML20112J383 ML20112J414
References
NUDOCS 8501180273
Download: ML20112J414 (8)

Text

P PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 130 November, 1984 t

t Y

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E 8501180273 850108 PDR ADOCK 05000267 R PDR

P 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 November, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Our new Power Plant Maintenance Information System (PPMIS) was put into service on November 5, 1984, and after a month of operation, most of the initial problems have been resolved.

After everyone becomes more familiar with this system, it should become a very important operating asset.

Construction has installed a new flow totalizer in our main tower blowdown line. This should give us a better indication of water chemi stry requirements, and make it easier to maintain proper circulating water chemistry.

Contractors working on the sewage lagoon dug up a 13KV feed cable from Bus 7 to various users, including the Visitor's Center and the Fort St. Vrain River structure. The Security Department maintained catalytic heaters in various areas to keep pipes from freezing. The cable has been repaired and returned to service.

"1A" Purified Helium Compressor Motor Generator Set failed on Thursday, November 1, 1984. Maintenance and the Electricians were successful in repairing the compressor and returning it to service.

Clearances were removed from "B" Helium Circulator, and after flushing of the bearing water piping and warm-up of the steam piping, the circulator was brought up to speed. The Inside Auxiliary Boiler was placed in service parallel with the outside boiler to attain the maximum circulator speed and helium flow.

This, as expected, showed a rise in primary coolant moisture.

However, after only a few days, the primary coolant moisture level reversed, to a downward trend.

The bearing water pump for Loop II, P-2102-S, had a bad seal.

This pump is necessary to operate Loop II circulators, because one other Loop II bearing water pump is inoperable. Since Loop I Helium Circulator, "1B", is operable, Loop II was shutdown and the bearing water pump repaired.

e

During the performance of a test of the reserve shutdown system for Control Rod Drive #21, the boron balls would not fully discharge from the hopper. This required a non-emergency event report to the Nuclear Regulatory Commission, which was reported on Monday, November 5, 1984 This malfunction is under investigation. We are continuing to perform back-EMF tests on the installed operable control rod drives.

"1A" Instrument Air Compressor periodically caused breakers to trip. The problem was investigated, and found to have a bad motor which has been replaced. Instrument Air Compressor "1C" unloading switch was functioning improperly. A new switch was installed, and still would not function at the desired pressures. A new switch is on order for the compressor. When both instrument air compressors are completed, "1B" will be removed for a scheduled five year preventive maintenance overhaul.

The Auxiliary Cooling Method (ACM) Generator Set is under going an oil cooler change out plus other work. While shutdown, the batteries are also being changed. "1B" Diesel Generator Set was removed from service to perform a scheduled preventive maintenance overhaul. "1A" Diesel Geaerator Set was taken out of service for a quarterly scheduled preventive maintenance c

overhaul. Both overhauls were completed, and both generator sets returned to service.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None.

-3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION Nore.

4.0 MONTHLY OPERATING DATA REPORT Attached.

2 e

75P-3 Att achmen t-3B Iszum 2 cirunx: cAn arror occa T so. 50-267 nan Dececber 14, 1984 caelzTo si Frank Novachek n:.trmxt (303) 785-2224 OPrM*.TNc STAI"J soTzs

1. unit ma e: Fort St. Vrain .

2. Repotting Period: 841101 throuah 841130

3. ucenaa Thermal Power (wt): 842

4. m.imeplate natins (cross we): ,

342

5. n.aisa nietrical nating (see me): 330

6. Maximia Denendable capacity (cross Wa): 342

7. u=w== Depudable capacity (Net we): 330

8. If changes occur in capacity Astings (items Nimaner 3 Throup.: 7) Since Imat Report, cive Ramaces:

None

9. Power Level Tc Whi.h Raatricted, If Amy (Net we): _,

280

10. naasons for mastriettona, If Any: Per commitment to the NRC, lona tenn operation above 85% power is pending completion of the B-0 Startuo Testino.

'1

. tis Month Yaar to Data Cumulative

n. nours in naporties period 720 8,040 47,521

12. Number of sours naaetor was critical 0.0 1.324.1 27,151.4 ,"

-13. maaetor nas - Shutdown sours 0.0 0.0 0.0

14. nours sener.cor on-Line 0.0 660.1 ,_

18,463.3

15. onic meserve shutdown sours 0.0 - 0.0 0.0

16. Gross Thermal Energy cenerated (w H; 0.0 340,407.9 9,861,725.3 l 17. cross rieetrical Energy cenerated (sv) 0 95,144 3,248,594 is. see Electrical Energy cenerated (wa) -2,803 58,889 2,930,419

~

19. Unit Service Tactor 0.0 8.2 38.9

20. unit Availability Tactor _

0.0 8.2 38.9

.tl. Unit capacity ractor (using nac see) 0.0 2.2 18.7

12. Unit capacity ractor (using Dra set) 0.0 2.2 18.7

23. enic rorced outage mate 100.0 85.6 45.7

24. Shutdowns Sebeduled over sext 6 Months (Type, Date, and Duration of rach):

12/01/84 through 03/31/85, 2904 hours0.0336 days <br />0.807 hours <br />0.0048 weeks <br />0.0011 months <br />, Control Drive Investigation.

25. If Shut Down at rnd of Report Period. Istir.ated Date of Startup: 04/01/85 4

26. Units In Test Status (Prior to co=sereial Operation): Torecast Achieved INInAL CRIUCM.In N/A N/A I:aTIAL trcnIcIn N/A N/A cort.Pc:A1 cr eA: os N/A N/A,_

. TSP-3 Attachment-3A i .

AVERAGE DAILY UNIT POWER LEVEL Issue 2 Paga 1 of 1 Docket No. 50-267 Unit Fort St. Vrain 4

Date December 14, 1984 Completed By Frank Novachek Telephone (303) 785-2224 Month November, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 05de-Net) (NWe-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 0.0 21 0.0 6 0.0 22 0.0 7 0.0 0.0

23

$ 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 ,

11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15' O.0 31 N/A 4

16 0.0

• Generator on line but no net generation.

w i

y. ..

. , . . . . . . 50-267 s

itNIT NAnt Fnrt St. Vrain .-

nATE .__Hecember_L4._19&4 CODeisTen av Frank Novachak

, REr0Rr NaNin November.1984 Tri.ernoNe f301M5-2224 W.1 MOD OF SNUTTINC posat SYSTEN COD 9'ONENT m). DATE TYRE DURATION REASON. REACTOR LER f WDE

,0)DE CAllSE AND 0)RRECTIVE ACTION 10 PREVFNT RFCitRPFNrE 84- 841101 F 720.0 A 3 50-267/84-008 AA ~JC Control Rod Drive Investigation 006

' t 4

We

o REFUELING INFOR.vATION I I i l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Schaduled date for next l 4th Refueling: l l refueling shutdown. I February 1,1986 l l l l l 3. Scheduled date for restart l May 1, 1986 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l l operation thereafter require a l 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? l l l 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

, I (Reference 10 CFR Section l l l 50.59)? I l 1 l l l If no such review has taken l 1985 l I; place, when is it scheduled? l l 1 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 1 l 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.

l analysis methods, significant l l l changes in fuel design, new l -l l operating procedures. l l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l_ spent fuel storage pool. I b) 143 spent fuel elements l 4.

REFUELING INFORMATION (CONTINUED) i I I 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. l l l l l l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-79ID01370 between l l charged to the spent fuel pool l Public Service Company of l l assuming the present licensed l Colorado, and General Atomic l l capacity. I Company, 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.

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