ML20112H722

Monthly Operating Rept for Dec 1984

ML20112H722
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1984
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
P-85008, NUDOCS 8501180009
Download: ML20112H722 (9)

Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION i

MONTHLY OPERATIONS REPORT NO. 131 December, 1984 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 December, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY R$ LATED MAINTENANCE The plant water district supply main was taken out of service on December 7, 1984, and returned to service on December 14, 1984.

Well #4 was in service to supply make-up water to the service water tower.

The alternate cooling method diesel generator was returned to service. It was started twice in a row by the electricians to prove that the new batteries were acceptable, and the unit was then loaded to 2500KW.

The Outside Auxiliary Boiler was chemically cleaned the week of December 10, 1984. This process was not tote.11y successful. An isolation valve and flange were installed on the boiler to facilitate chemical cleaning. This cleaning was started on December 20, 1984, and completed on December 21, 1984 Safety valves on this boiler are being repaired.

The clearance was removed on "C" Instrument Air Compressor and the compressor was started and operated. Instrument Air Compressor "1B" was then cleared for a five year preventive maintenance overhaul.

LV-21114 was cleared out for repair on December 19, 1984. This required a shutdown forced cooling while the valve was removed and 'ianges were installed on the piping. "D" Circulator was ther restarted for decay heat removal purposes while the valve is being repaired.

One cell on "1A" battery was found to be bad. It has been removed and will be replaced with a new cell. "1A" battery charger has several problems and investigation continues. The

, " Loss Of Outside Power" surveillance will be performed when the problems are resolved.

The engine heaters on "1A" diesel generator were turred off on December 27, 1984 to allow the engines to cool down to test their cold starting capability. This test was successfully completed on December 29, 1984.

The Rucker unit has been repaired and "A" Circulator was removed from the vessel on December 28, 1984, and shipped off-site on

, December 29, 1984.

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We are continuing to investigate the purified helium header moisture problems. This investigation is limited by the need to maintain primary coolant circulation and pressure. The elements involved are required for a pressure control path for primary coolant.

The new Clearance, Temporary Configuration Report, and Operation Deviation Report Tagging Procedure was presented to all licensed operators during the third requalification session.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXp0SURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION None.

4.0 PONTHLY OPERATING DATA rep 0RT Attached.

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_ . _ _ . . _ _ _- l w-s Atttchamat-3B Istus 2 Ortunw: MTA REPORT DOCKET NO. 50-267 un January 4. 1985 courunD nT Frank Novachek m . armour (303) 785-2224 OPERAm*O STATUS rons

1. unit u.a.: Fort St. Vrain .

2. asportins Period: 841201 throuch 841231

3. Licensed Thermal Power 06ft): 842 _

4 Nameplate Rating (Gro.a Ne): 342

5. Design Electrical natins Diet me): 330

6. Mari== Dependable Capacity (Gros. We): 342

7. Nart== D.pendable Capacity (Net We): 330

8. If chanses Occur in capacity Ratinse (Items Number 3 Through 7) since last Report, Give Reasons:

None

9. Power Level To Ubich Restricted If Any Olet m ): 280

10. naaeons for nestrictions, If Any: Per commitment to the NRC. lona term operation above 85% power is cending completion of B-0 startup testing.

This month Year to D.te Cumulative i n. nours in s. porting period 744 8,784 48,265

12. Number of nours ameter v u critie 1 0.0 1,324.1 27,151.4 ,'

13. n= eter n erve shutdown uo.r. 0.0 0.0 0.0

14. nour. Generator on-u 0.0 660.1 18,463.3

15. unit m e erve shutdo a sour. 0.0 . 0.0 0.0

16. cro . Ther= 1 z rsy Gen. rat.d (w a) 0.0 340,407.9 9,861,725.3 0 95,144 3,248,594

17. Gro.. Electrical Eners' Generated Olla) is. n t nectrical z=rar Generated (wa) -2,461 56,428 2,927,958

19. unit S'ervice rector 0.0 7.5 38.3

20. unit availannity r etor 0.0 7.5 38.3

n. unit capacity rector (usins noc z.t> 0.0 1.9 18.4 l

22. unit capacity rector (u. ins Dra met) 0.0 1.9 18.4

3. unit rore.d outas. mate 100.0 87.6 46.8

24. shutd sched.1 4 over ses 6 nonths (Type Date, and Duration of Each): 01/01/85 through 03/31/85, 2160 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.2188e-4 months <br />, Control Rod Drive Investigation.

' 04/01/85 4

5. If shut Down c sad of a. port p.riod, z.timat.d D t. of startup:

26. units In *est status (Prior to commercial Oper. tion): Forecast Achieved IsmAL ca:nCAI.nT N/A N/A IrInAL z:.remenT N/A N/A coMERCIAL OFEaA n0N N/A N/A i

TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date January 4, 1985 Completed By Frank Novachek Telephone (303) 785-2224 Month December, 1984 -

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVE:.

(We-Net) (MWe-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 0.0 21 0.0 5

0.0 0.0 6 22 7 0.0 23 0.0 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

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13- 0.0 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 l l l 2. Scheduled date for next [ 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 l (Reference 10 CFR Section l l l 50.59)? 1 l l l l l If no such review has taken l 1985 l l place, when is it scheduled? l l 1 l l l 5. Scheduled date(s) for submit- l l ting proposed licensing action l ---------=

l l l and supporting information. l l l l l l 6. Important licensing considera- l l l tions associated with refuel-- l 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 i

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, , l 7. The number of fuel assemblies l 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 r

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REFUELING INFORMATION (CONTINUED) l l 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.- l l

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l l l 9. The projected date of the last i 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 feel segment will be discharged in 1992.

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. . 16805 WCR 19 1/2, Platteville, Colorado 80651 January 10, 1985 Fort St. Vrain Unit #1 P-85008 Office of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

REFERENCE:

Facility Operating License No. OPR-34

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of December, 1984.

Sincerely, q N. b p J. W. Gahm i Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm v

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