ML20128C067

Monthly Operating Rept for Apr 1985

ML20128C067
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85167, NUDOCS 8505280169
Download: ML20128C067 (9)

Text

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• Atttchment=3B Iccua 2 v orrunuc un arronT DoCxrt no. 50-267

- myE May 9, 1985 Court.rTzD sf Frank Novachek Tztzenowr (303) 785-2224 OPERATING STATUS soTzs

1. unit na.e: Fort St. Vrain ,

2. Reporting Period 850401 through 850430

3. Licensed Themal Power ()6TC): 842 4 Nameplate Rating (Groes 3Gie): 342

3. Design Electrical Rating (Met IGle): 330

6. Mad == Dependable Capacity (Gross leie): 342-

7. Nad- Dependable Capacity Olet late): 330

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

None

9. Power Level To Which Restricted If Any (Not pale), 280 lo. naasons for mastricts es, If any: Per commitment to the NRC, lona term operation above 85% power is pending completion of B-0 startup testing.

T21s Month Year to Date C M ative

11. nova in n porting period 719 2,879 51,144

12. number of a.ua n etor v s Critte.1 0.0 0.0 27,151.4 l

13. manctor meserve shutdown nones 0.0 0.0 0.0

14. news ca ator on-I,ine 0.0 0.0 18,468.0

15. Unit Reserve Shutdown Bours 0.0 0.0 0.0

16. Cross Themal Energy Generated OSfa) 0.0 0.0 9,861,714.4

.17. Cross Electrical Energy Generated Osin) 0 0 3,248,594 la. set necerical Energy cenerated (isra) -1,966 -8,048 2,919,910 l

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19. Unit S'ervice Factor 0.0 0.0 36.1

20. unit Availability Factor 0.0 0.0 36.1

21. Unit capacity Factor (Using MDC Net) 0.0 0.0 17.3 h 22. Unit Capacity rector (using der set) 0.0 0.0 17.3

23. Unit rorced outage mate 100.0 100.0 50.9

,g 24. Shutdowns Scheduled over Neat 6 lbaths (Type. Date, and Duration of Each): 850501 through 850615 l9 1.104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, control rod drive refurbishment and circulator bolting changeout. .

, 0 ac 850616 4

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

26.' 12its In Test Status (Prior to Commercial operation): Forecast Achieved a N/A N/A or n:IUAL CRIUCALITT .

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, ME . I InAL ELECTRICITT N/A N/A I. 't l

l. ConesaCut orsmATIos N/A N/A

(. TSP-3 Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL hm 2 '

Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date May 9, 1985 Completed By Frank Novachek Telephone (303) 785-2224 l

Month Aoril .1985 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Nie-Net) (NWe-Net) 1 0.0 17 0.0 2 .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 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 13, 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 N/A 16 0.0

• Generator on line but no net generation.

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REFUELING INFORMATION I~ - -

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.l 1. Name of Facility 'l Fort St.-Vrain Unit No. 1 l l l l l 2. Scheduled date for next l 4th Refueling: l

-l refueling shutdown. l February 1,1986 ' l

-l . .

l l ll~3. Scheduled date'for restart. l May 1, 1986 l

'l - following refueling. l l

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..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 1 - .

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)? I l l- . l l l If no such review has taken l 1985 l l ' place, when is it scheduled? l l l- ~

l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action-l ---------------- l l 'and supporting information. 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) 137 spent fuel elements l Y

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2 REFUELING INFORMATION (CONTINUED)'

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-l l l 8. -- The pre'sent-licensed spent fuell l lL pool storage _ capacity-and the ~ l .

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- l. isize of any increase in .

l Capacity is-limited in size to l-

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.' l- ;1icensed: storage capacity-that l about:one-third of core- -

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-l. - has been requested or. is _ l (approximately 500 HTGR elements).1

planned,.in number of fuel;.

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l No change.is planned.

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- l- ' assemblies. 1 l l .. . _

. -l I 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. l Company,-and DOE.* l-A 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 Idahor. Chemical Processing . Plant.

The storage capacity has evidently been' sized to accomodate ;eight fuel segments. It -is H

Jestimated that.the~ eighth fuel segment will be discharged iri 1992.

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

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MONTHLY OPERATIONS REPORT N0. 135 APRIL, 1985

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syg .;This s report icontainsf the. highlights s of; ;the Fort St. Vrain, Unit W Noici,Jactivities doperated under the provisions of; the :Nuclea'r D' ' '

' _ Regulatoryh Coinmiss' ion 10perating License DPR-34. JThis report 'is for

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the month offApri.1,:1985.x

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'e L il'.0 NARRATIVE":

SUMMARY

OF OPERATING EXPERIENCE' AND MAJOR ' SAFETY

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4 RELATED MAINTENANCE g  ;

, ~The-reheatfstopcheckvalvex-rayingisessentially.completeand '

?, X , ithe': extent of weld repairing: required has beenE determined. The ~'

, weldGre'pairsJare in progress and.~.will'take!several weeksito

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complete. 4Thefvalves.will then.be reassembled and t'ested.

@', ;TheJControl' Rod / Drive Refurbishment' Program continues. As of 1~ ~ fAprill30,<1985,' twenty-five (25) Control-Rod Drives are either in_

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rework or.have been reworked and returned to the core.

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* .The.J'1A'.:and '1B Station Battery' electrolytes'have been changed eand.the batteries-have been'. recharged. .Several dischargeiand ,

d, Y -loa'd ytests: were performed to, test.the batteries' capacity. The

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, batteries were then recharged and are. now being monitored for, specific = gravityNand charge maintenance capability. Both '1A'

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p 1 and7-'1B' batteries are operational.

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,; Progress? continues. on' the I-01/I-02 modification for. Human-It is presently-.65% complete.

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Factors considerations.

4,

.TheKair. compressors continue ' to cause. maintenance problems.

.y  ; , .Several changes to-the maintenance' rebuild procedure are being

, y . ; implemented. The results will be evaluated after the' compressors .

-are returned to service.

Helium > Circulator- '1A' has been replaced in the PCRV, and the aK circulator was returned to service on, April 25,-1985. This circulator had been

- n sent to GA Technologies for ' repair of-a l 1

-bearing waterfinterspace leak. It also had experienced. chloride '

sm~' : ,

stress problems 'on some bolting'which has since'been replaced; 1 . The '.1A' Circulator Main Drain Valve! has been' removed and p replaced. with ;a digital valve and electronic controls. This

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system 'will be used as a pilot' project to determine the similar' valves

-feasibility' o f. - installing on the other

. ' circulators;

,, ,' '(Helium ' Circulator '18.' has been removed from the PCRV to replace

~... interna 1Lbolts. The. circulator ' bolts were replaced and the 1_'t*

circulator- was reassembled. The circulator is'now installed in the PCRV,'and leak checked. External piping, assembly is in Mi - progress.- ; Helium Circulator '10' piping is being removed in I~fj fpreparation'~for Helium' Circulator '10' removal ~ and bolt

.c .f 1. .- ,

'changeout.

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i._J - -: The . annual . Requalification examinations are in progress. The

. ~ Nuclear Regulatory Commission .will be on site in ~May to

-administer. -oral, 'and written examinations to the Nuclear Regulatory Commission selected license holders.

-Numerous 1 plant design changes are being installed and tested.

These include but are not limited to, changes on, the purified helium header, circulator auxiliary system monitoring capability p and human factors control board modifications.

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 EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT

, , .  : Attached 1[ '

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O PublicService . ,..

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 May 13, 1985 Fort St. Vrain Unit No. 1 P-85167 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 - April, 1985 l-

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed pletse find our Monthly Operations Report for the month of April, 1985. -

Sincerely, J.

Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:dr Enclosure cc: Mr. John T. Collins

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