ML20205A396

Monthly Operating Rept for Mar 1985

ML20205A396
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85126, NUDOCS 8504250503
Download: ML20205A396 (9)

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

MONTHLY OPERATIONS REPORT NO. 134 March, 1985 f 5

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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 March, 1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The Control Rod Drive refurbishment is progressing. Numerous problems, primarily with respect to spare parts delivery, have delayed the overall program. To date, seven (7) Control Rod Drives have been completed.

The station battery "1A" electrolyte has been changed and the batteries recharged to resolve the performance problems experienced early in the month. Several discharge and load tests have been performed to test the battery capacity. The batteries are now being monitored for specific gravity and charge maintenance capability. No decision has been made on the battery operability at this time. Manufacturer's representatives are working with plant personnel to resolve this problem.

- Loop II Steam Generators and Helium Circulator "1D" continue to

provide primary coolant flow and secondary cooling capability.

Reactor Liner Cooling Water, Loop II, is isolated from service for system valve rework. Loop I is currently providing liner -

cooling.

Helium Circulator "1A" has been returned from San Diego, and installation is estimated to be complete by April 4,1985.

Helium Circulator "1B" will then be removed for repairs and inspection.

The Reheat Stop Check Valves on Loop I and Loop II are being X-rayed to determine the extent of body repairs that will be required prior to returning the valves to service. The X raying requires several days of off shift effort for each valve and to allow for normal day shift activities and area access. The Hydraulic Operator for each of the valves is scheduled to be received from the operator rebuild contractor later in April.

The Instrument Air Compressors continue to cause operational problems. Efforts are underway to determine the cause of the substandard performance. Several changes to the maintenance overhaul procedure are being investigated. The results will be evaluated after the compressors are returned to service.

The " Loss Of Outside Electrical Power" surveillance was performed on March 18, 1985. The backup power system performed as expected i and all systems were returned to normal supply.

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A personal accountability drill was performed on March 28, 1985.

l The rewrite of the Technical Specifications continues, and personnel are reviewing and commenting on the rewrites.

Eight (8) Itcensed personnel will be taking the annual Nuclear Regulatory Commission exams in May.

Numerous plant design changes are being installed and tested.

These include, but are not limited to, changes on the Purified Helium Header, Circulator Auxiliary monitoring capability, and Human Factors Control Board modifications.

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 A

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757-3 Attrchment-3B 3 * ,*- Issue 2 oPERAT1?:C DATA REFoRT DOCKET No. 50-267 ,

DATz ' April 11.1985 ConruTED RT Frank Novachek TEz.ErnoNr (303) 785-2224 OPERATING STATUS NonS

1. omit Nan : ' Fort St. Vrain .

2. m.portins Periods . 850301 throuoh 850331

3. ucensed Thernal Power (Wt): _ 842

- 4. Nansplate Rating (Gro.s We): 342

5. Design Electrical Ra' ting (Net We): 330 ,

6. N=d== Dependable capacity (Cross We): 342

7. Mad == Dependable capacity (Net We): 330

8. . If Changes Occur in Capacity Ratings (Ites. Number 3 Through 7) Since fast Report, Cive Raasons:

-None

9. Power Level To Which Restricted, If Any (Net We): 280 Per commitment to the NRC, long term operation above

-10. maasons for mastrictions, Ir any:

85% power is pending completion of 8-0 startup testing.

This Month Tear to Date cumulative

11. nour. in napartins reriod 744 2,160 50,425 0.0 0.0 27,151.4 ,

12. Number of sours nactor wm Critical. _

13. maaetor me.orve Shutdown Bour. 0.0 0.0 0.0 0.0 0.0 18,468.0

14. nour cenar cor On-une

15. Unit Reserve Shutdown Hour. 0.0 0.0 0.0 ,

16. cro.. Thermal snergy can.rae.d (Wa) ,

0.0 0.0 9,861,714.4 cro.. riectrical znersy cenerated (Wa> 0.0 0.0 3,248,594

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' -2,187 -6,082 2,921,876

.la. Het n.ecric 1 Enerar cenerated (Wa) 0.0 0.0 36.6

19. Unit S'ervice rector

20. Unit Availability Tactor 0.0~ 0.0 36.6

21. enit Capacity recter (usins xaC Net) 0.0 0.0 17.6

22. Unit capacity Factor (Using DER Net) 0.0 0.0 17.6

23. Unit Forced Outage Rate 100.0 100.0 49.9 I

24. Shutdowns Scheduled over Next 6 Months (Type. Date, and Duration of Each): 850401 throuah 850614.

l-1800 hours, Control Rod Drive refurbishment and circulator work.

850615 4

25. If Shut Down at End of Report Period. Estimated Date of Startup:

! 26. Unit. In Test Status (Prior to Cotunercial Operation): Torecast Achieved i .,

IxinA1, CMnCAun N/A N/A mnAI. EucTuCIn N/A N/A t

co wzRC ut. orERATIos N/A N/A L

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• Attachment-3A l Issue 2 AVERAGE DAILY UNIT POWER LEVEL Pag 2 1 of 1 ,

Docket No. 50-267 Unit Fort St. Vrain Date April 11,1985 l

Completed By Frank Novachek Telephone (303)785-2224 Month April,.1985 _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 0.0 17 0.0 1 1 0'. 0 18 0.0 l 2

3 0.0' 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 1 7 0.0 23 0.0 0.0 24 0.0 8

0.0 25 0.0 e 9

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'10 26 ,

0.0 0.0 f 11 27 0.0 0.0 i 12 28 0.0 29 f 0.0 30 0.0 14 I 0.0 31 0.0 15 16 0.0 l

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• Generator on line but no net generation.

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REFUELING INFORMATI,0N I. I I l -1. 'Name of Facility ~ l Fort St. Vrain Unit No. 1 _I l . I l l 2. ' Scheduled date for next -l 4th Refueling: l l refueling shutdown. I February 1, 1986 l

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I I 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 1. l l or other license amendment? l l l l 1

-l- If answer is yes, what, in I ---------------- 1 I general, will these be? l l

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I I I If answer is no, has thereloadl 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 (Reference 10 CFR Section l l.

l 50.59)? l l

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I- l l If no such review has taken l 1985 l l place,-when is it scheduled? I l l l 1 l 5. Scheduled'date(s) for submit- l l l . ting proposed licensing action 1 ---------------- 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 ing, e.g. , new or different l I l fuel design or supplier, unre- I ---------------- 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 I l l I l 7.- The number of fuel assemblies l l l (a) in the' core and (b) in the I a) 1482 HTGR fuel elements  !

,l spent fuel storage pool. I b) 137 spent fuel elements l

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• REFUELINGINFORMATION(CONTINUED}

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1 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).1

-l. planned, in number of~ fuel l_No change is planned. l l assemblies. l- l l .

l l ll 9. -The projected date of the last l 1992 under Agreements AT(04-3)-633]

l refueling that can be dis- l and DE-SC07-791D01370 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. l 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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16805 WCR 19 1/2, Dlatteville, Colorado 80651 April 15, 1985 Fort St. Vrain Unit No. 1 P-85126 Office Of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Monthly Operations Report - March, 1985

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

Sincerely, l

. /W

/J.W.Gahm Manager, Nu: lear Production l Enclosure cc: Mr. John T. Collins JWG/djm

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