ML20235Z416

Monthly Operating Rept for Sept 1987

ML20235Z416
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/30/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87364, NUDOCS 8710210132
Download: ML20235Z416 (8)

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Psee 1 'f-1 cPERATrne DATA Pz7er- DoctET c . ..50-267 L ,

DATE October 15.-1987 ConrLETED BT F. J. Novachek TELEPHONE (303) 620-1007 OPERATINO $ TAT'JS NOTES

1. Unit same: Fort St. Vrain, Unit No. 1  !

' 2. Reporting Period: 870901 through 870930 ,

3. ' Licensed Themal Power (Wt): 842

4. Naneplate Rating' (Crosa We): 342

5. Design Electrical Racing (Net We): 330

6. Maximum Dependable Capacity (Cross We): 342

7. Hazimum Dependable Capacity (Net We): ' 330 I

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:  !

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9. Power. Level'To Which Restricted, If Any (Net We): 270.6 [

10. Resaons for F -91ctu,rc If Any: Reanalysis of safe shutdown cooline followine a 90 minetL;bterruption of forced cooline.

l This Month Year to Date Cumul6tive  ;

n. vours in Reporting period 720 6,551 72,336

12. Number of Hours Rese.3e Was Critica,1 20.9- 2,413.3 32,951.I

13. Reactor Reserve Shuu r.in P.ours 0.0 0.0 0.0 l

14. nours cenerator on-Line 0.0 1,811.7 21,366.8

15. Unit Reserve shutdown sours 0.0 0.0 0.0 l 16, cross Thert : Energy ceneracea (Wu) 86.1 576,632.2 10,842,032.0

17. cross Electrical Energy ceners,.ed (Wu) 0.0 189,789.0 3,523,785.0

18. Net Electrical Energy Generated (MI) 0.0 157,908.0 3,106,188.0 t I

19. Unit Service Tactor 0.0 27.7 29.5 '

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20. Unit Ava114,ility Factor 0.0 27.7 29.5 1

21. Unit Capacity Tactor (Using MDC Net) 0.0 7.3 7.3 l hg 22. Unit Capacity Factor (Using DER Net) 0.0 7.3 7.3 ONA gC 23. Unit Forced Outage Rate 100.0 72.3 63.7

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Fire Recovery

.'h (D o 871003. 1080 hours0.0125 days <br />0.3 hours <br />0.00179 weeks <br />4.1094e-4 months <br /> bio 25. If Shut Down at End of Report Period. Estimated Date of Startup:

no Novemhnr 15. 19A7 OA w<

rd 26. Units In Test Statua (Prior to Cornercial Operation): Torecast Achieved O'

Q :NITI.AL CRITICALITY N/A N/A INITIAL ELIc21cm N/A N/A ')

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Completed By F. J. Novachek. ]

' Telephone (303) 620-100/-

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Month  : SEPTEMBER DAY..' AVERAGE DAILY POWER LEVEL .D'AY AVERAGE. DAILY POWER LEVEL-

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REFUELING INFORMATION

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. I Name'of Facility fl. l. I' Fort St.'Vrain Unit No. 1

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, lc2. . Scheduled date for next. .1 l-4 i

-1" refueling shutdown. -l January 15, 1989 j.

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~l'3. . Scheduled date for restart- -! March'15, 1989 l-

.- l following refueling. l l

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,., ;l 4. 'Will refueling or resumption ofl No. l h

'l -operation-thereafter require a l l

l' technical specification change l l-l! or other lice'nse amendment? I l l -- l l ..

ll ' If. answer is yes,what, in I ---------------- -l-l'

-l general, will these be? . I l

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If. answer.is no, has the reload l l ll fuel design and core configura-l l --

l~ tion been: reviewed by your .l' l Plant Safety Review Committee l No l' to determine whether any unre- l 'l' tl- ~ 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

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- l( If no'such review has taken l 1988 l l place, when'is it scheduled? l l l'.

l5 Scheduled date(s) for submit- l l

ting proposed licensing action l ----------------

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l and supporting information. i 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 l viewed design.or performance l l l

l analysis methods, significant l [

. l. changes in fuel design, new -l l l operating procedures. 1 l l I 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) 0 spent fuel elements _l J

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, ' ' -REFUELING INFORMATION'(CONTINUED) 4

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g;.l[8'.:The'present.'licensedspentfuell. '

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.. l 7 ' size of any increase in' ' lLCapacity.isilimited:in size to- ,(

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licensed- storage capacity that -l about,one-third of' core l

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has been requested or.is- - l.(approximately'500HTGRelements).-l

1. planned,;in number'of fuel l' No change is planned. l' assemblies. I'

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l I h 4 . l; 9. The projected date, of the last l 1996 'under Agreements AT(04-3)-633) fl refueling that can be' dis-- . l_and DE-SC07-79ID01370 between ~ -l

- li -charged to theispent fuel pool'l Public Service Company ofL ll S. , T  : l-l { assuming the present licensed l-Colorado,Eand General: Atomic l

, l ~ capacity.- 1 Company',=and DOE.* ' ]-

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• The 1996 estimatUd date-is based on:the underst'anding'that spent fuel _-

' discharged during-the term of.:the Agreements will" be stored by DOE'at xthe1 Idaho Chemical: ' Processing . Plant. . The storagei capacity has

' evidently been' sized to. accommodate'.eight fuel ~ segments,. JIt.-is'

.4 estimated that the: eighth-fuel segment.will be-discharged in 1996,-

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16805 WCR 19 1/2, Platteville, Colorado 80651 October 15, 1987 Fort St. Vrain (

Unit No. 1 P-87364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

SEPTEMBER, 1987 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License No. DPd-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of September, 1987, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely,- i E l)$Y $Y

~=o R. O. Williams, Jr.

Vice President y f Nuclear Operations v2

-9 Enclosure g cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain R0W:djm 7 d

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l MONTHLY OPERATIONS REPORT

, N0; 164 September,'1987 I '1, i

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1 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 No. DPR-34. This report is  ;

for the month of September, 1987. '

i

-1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY l RELATED MAINTENANCE l The' reactor was taken critical for the purpose'of licensed  ;

operator training startups and NRC examinations at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> on --

September 10, 1987. The reactor was manually shutdown at 2004 l hours on September 17, 1987.

The operability of all four helium circulators on simulated boosted firewater vas tested following the reactor shutdown.

Test results indicated 'A' helium circulator Pelton wheel drive l did not deliver the- required power. The reactor was depressurized on September 19, 1987, and 'A' helium circulator l Pelton. wheel drive was inspected. One of two nozzles for the Pelton wheel drive was discovered to be completely plugged by a bolt that had lodged in it.

The bolt was removed and 'A' helium circulator was returned to service on September 27, 1987.

The reactor was taken critical at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br /> on September 30, 1987. l 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE i

None  !

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS 1 i

None  !

4.0 MONTHLY OPERATING DATA REPORT Attached l-

.