ML20138J549

Monthly Operating Rept for Nov 1985

ML20138J549
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85468, NUDOCS 8512170559
Download: ML20138J549 (9)

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PUBLIC SERVICE COMPANY OF COLORADO

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FORT ST. VRAIN NUCLEAR GENERATING STATION

[~1 MONTHLY OPERATIONS REPORT I NO. 142 November, 1985 f

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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 -

Regula .ory Commission Operating License DPR-34. This report is for the month of November, 1985.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY

.RELATED MAINTENANCE

The plant operated at approximately 7 percent rated thermal power

!! from the beginning of the month to November 7, 1985. Shutdown was then initiated to facilitate Environmental Qualification work, and the reactor was shutdown from less than 1% power on November 8, 1985.

The annual Institute of Nuclear Power Operations Evaluation at i

Fort St. Vrain was conducted November 4 through November 15, 1985.

Throughout the month, "D" helium circulator exhibited unusual behavior that indicated problems with the buffer helium system and/or the shutdown seal. Several days were spent troubleshooting with Test-301 and it was determined that HV-2190-4 and/or HV-2190-7 (helium / water drain valves) were leaking through. Repairs will be subject to parts procurement.

A planned loss of forced cooling was taken November 18, 1985, while the semi-annual " Turbine Trip and Loss of Outside Electric 1 Power" surveillance test was being successfully completed, k

j. The chemical layup of feedwater heaters 5 and 6 was completed on November 27, 1985.

During the month of November, quarterly, semi-annual, and annual l

preventive maintenance on emergency diesel units K-9205X and K-9206X was completed.

Work is continuing on the Environmental Qualification (EQ)

Program. As of November 30, 1985, approximately 9.5 percent of the EQ Station Service Requests (SSR's) generated as a result of the Nuclear Engineering Division Walkdown have been completed.

Another 23 percent of the SSR's are in progress. Prior to startup, as much work' as possible will.be completed on the , -

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Reserve Shutdown System, "A" and "C" Helium Circulators, and "B" Instrument Air Compressor. Scheduling and Operations personnel .

are evaluating the EQ Master Equipment List to determine which items can be worked with the Reactor at power.

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.- 2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS

{, OF 10% OF.THE ALLOWABLE ANNUAL VALUE -

None , .

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3.0 INDICATI'ON OF FAILED FUEL RESULTING FROM IRRADIATED FUEL ,

-EXAMINATIONS

.None  ; >

4.0 MONTHLY OPERATING DATA REPORT

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• Issue 2 OMMTINC DATA RIPORT DOCKET KO. 50-627 can December 10. 1985 g

com.tnD af Frank J. Novachek

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Trttraoxe .(303)'785-2224 CP!MTING STATt'5 ~~~

riOIES

1. Unit x4==: Fort St. Vrain

[ 2. Reporting Period: 851101 through 851130

~. 3. ' Licer. sed Ther=al Pever (Mit):

042 l\ 4. ; Nameplate Rating'(Cross We): 342

~5 330

5. ! Design tiectrical Rating (Net NJe):

'6. Maximes Dependable Capacity (Cross We): -342

7. Maximus Dependable Capacity (Ket We): 330 . _

8. ' If Changes occur in capacity Ratin5s (Items Number 3 Through 7) Since Last. Report, Cive Reasons:

None A

9. Power Level To '.*hich Restricted, If Any (::et We): 280

. 4, 10.- - Reasons for Restrictions. If Any: Per commitment to the NRC, long term operation above 85% power pending completion of B-0 startup testing.

This Month Year to Date Cumulative  !

7- 11. sours in neporting period 720.0 8.016.0 56,281.0

12. sueer of sour neaeter tas critical 167.0 929.8 28.081.2

':3. n. actor Reserve shutdown sours 0.0 0.0 0.0 " -

is. nours cenerator en-tine . 0.0 0.0 -

18,468.0 15.- Unit Reserve Shutdown Hours 0.0 0.0- 0.0 j

/16. cress :het : rnergy cenerated (su) 8,947.7 33,368.8 9,895.083.2 ___.

17. cross Electric.1 energy. cenerated (naa) 0.0 0.0 3.248,594 sa. ret tiectrical energy cenerated (mu) -3,332.0 -28,538.0 2,899,420

19. .cnic Service r.ctor ,

0.0 0.0 32.8 o% .

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0.0 0.0 32.8

. ,,,; 20. , rnit Avat:atitty ractor L 21. rnit Capacity ractor (estos nac xet) 0.0 0.0 15.6

22. :nic capuity ractor (csing Det see) 0.0 0.0 15.6 100.0 100.0 56.8 ~.

23. enic rcreed outage gate _

Shutdowns Scheduled over ;*axt 6 n:nths (? None 26 f pe, Date, and Duration of tach):

25. If Shut Down at End of Xepert Period. Estir.ated Date of Startup December 21. 1985

26. Calts In Test 5:stus (Prier to co c.ercial Opera tion): Torecast Achieved

); istria cur:CurrT N/A N/A i 151TIA1 EdC7MCtre N/A N/A N/A N/A fV cCn:nc:a orturica m AM

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" - = AVERAGE DAILY UNIT POWER LEVEL. Page -1 of 1 Docket No. 50-267 Unit Fort St. Veain -__

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- Date Decmeber 10, 1985 completed By Frank J. Novachek Telephone (303) 785-2224 Month November-

- DAY ' ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWe-Net) _ (ige-Ne t)

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1- 0.0 17 0.0

. '2 0"0 . 18 0.0 3 -0.0 19 0.0 .

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.- 4 0.0 20 0.0 5 0.0 21 0.0 -

6 0.0 22 0.0

'7 0.0- 23 0.0 .

8 0.0 24 0.0

-9 0.0 25 0.0 10 0.0 26 0.G 11 0.0 27 0.0 12 0.0 28 0.0

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29 0.0 14' 0,0 30 0.0 15 0.0 31 N/A 16 0.0 -

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^ Generator on line but no net generation.

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. lease 2 UNIT 518UTINants AllD TOWER REDUC~~

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50-267 i.,cxr.T no. - '

unir mane Fort St.:Vrain ,.,

nnTe December 10, 1985 corrierra av Frank J.'Novachek >

REroRT PENETil December ret.r.ruone (303) 785-2224-eumain or 6 :j.

sutrmsn IWN SYKir.H . Corrottr.nr ',

no. aarr. Tyre nunartou nrason neacron aza a conc cone- cAttse Anu coanccrive Acrton to ratverar necunar.nce '-

'85-00' 851108 F .. 546.5 hrs D 2 N/A- _ZZ ZZZZZZ Environmental Qualification' t

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REFUELING INFORMATION I I I l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. l April 1, 1987 l l I I l 3. Scheduled date for restart l May 1, 1987 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 1 1 I 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 reloadj 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 1 1 I l 5. Scheduled date(s) for submit- l l l ting proposed licensing action 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 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 - 1 l

l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 137 spent fuel elements l

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REFUELING INFORMATION (CONTINUED) 1, 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 .

E l -planned, in number of fuel l No change is planned. l l assemblies. l l l i 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

.I 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 accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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Companyof Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 December 13, 1985 Fort St. Vrain Unit No. 1 P-85468 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 For November, 1985

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month af November, 1985.

Sincerely,

/d

'/ J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. Robert D. Martin Regional Administrator, Region IV JWG:djm 4

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