ML20028E647

Monthly Operating Rept for Dec 1982

ML20028E647
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/10/1983
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20028E645	List: ML20028E644 ML20028E647
References
NUDOCS 8301280080
Download: ML20028E647 (8)

Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 107 December, 1982 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 tne month of December, 1932.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The steam generator leak was determined to be in Loop 2 steam generator module B-2-3 subheader "m". The elevation of the leak was determined to be in the superheater 2 bundle. The steam generator repair was completed on December 22, 1982.

The reactor was brought critical on December 23rd and increased to less than 2% power. The storm prevented delivery of enough fuel cil to meet cur minimum storage requirement of 20,000 gallons to exceed 2% pcwer. We received emergency assistance from Johnson's Corner and Bukrus 011. Reactor power was increased to 8% on December 28, but the reactor scrammed due to a spurious moisture monitor trip. The reactor scrammed again on December 29 from another moisture monitor trip but was critical again on December 30th.

Several problems were experienced during the month with both the inside and outside auxiliary boilers. The outside boiler has experienced problems with the burner assembly and the positioner for the fan dampers. The inside boiler has had some problems with tne fire eye.

The leak in "B" purification cooler results in the system sometimes becoming gas bound. Methods of dealing with the ingressive gas have been evaluated by Engineering, and it is anticipated the modification work will start shortly.

There were some problems in the gas waste system during the

! month whicn resulted in damage to "B" gas waste compressor. The gas waste compressor is being disassembled and evaluated. The reason for the water in the gas waste vacuum tank is being i investigated, and several potential sources are being considered.

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

1 3.) !NDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None i -

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2 4.0 MONTHLY OPERATIrlG DATA REPORT Attached

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" ' I * ' 1 cPrurr:c DATA RIP??T cocn! ::o. 50-267 pris January 10, 1983 c:s:. Tra 3Y I.. M. McBride T ttrac:;r (303) 785-2224 CPEMT!':c STAft*5 1 ::orr.s

1. cni: Nane: _ Fort St. Vrain

. Repse: ins Peri:d: 821201 through 821231 3 License 3 Thernal Psver O*Jc): 802 L. :la eplate Rating (Gross :"Je): 342  ;

5. :esigi Zieetrical Ra:ing c:e: .5;e): 330  !

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4. "4ximum :ependable Capa:ity (Cross Pie): 342 i

7. :uxi=us cependahte capa:1cy c:et ::ce): 330

3. If Changes occur in Capacity natings (Items Nu=ber 3 Through 7) Since tast Report. 01ve Kessens:

None

?. F:se *.evel To *.hich Festricted. If Any (set Pie): 231

10. Kessons for P.estrictions, If Any: Restriction to 70% oending resolution of

_c,pn P ra c tu 11 ma t t e r s This yon:5 Year to 34:e Carulative

1. Hours in F.eporting Peried 744 8760 30721

1.  ::u:5er of noues asse:ar :4s Ori:ical 423.3 5168.3 ,19746.7

u. Res:: r reser<e shutto n x;urs 0.0 0,0 0,0 t.. Heurs ceneracar en-Line 0.0 3266.2~ 13174.5

15. tal: Reseree shu:down Hours n0 0.0 0.0 l'3 . Gross Thermal Enery.r Genera:ed (:2.3) A_101_1 1_q55.4RO.6 6.78o.425.4

17. Cross Ele:trical Eaersy Generated (!Ld) n 615_549 2_126.o04

u. nec tiee:ricat :ner;y cenera:e4 (r.ca)

-4,234 568,851 2,123,110

u. Uni: servie rae:ar 0.0 37.3 42.9

23. rnic Availadtlicy rae:or 0.0 37.3 42.9

21. cnic capaci:y rae:ct (tsing :cc ::e:) 0.0 19.7 20.9

22. Uni: ca;2:tcy rae:or (tsing :ta see) 0.0 19.7 20.9

3. cnic rarce4 au:2ge xace 100.0 44.3 36.9

a. Shutlevns Scheduled Over Nex: 4 bn:hs ("ype. Ca:e, and ruratian of Isch): Plant recovery 83010t - 11.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Surveillance testing S30323 through 830412 - 504.0 hou!s.

5. If shac Down a: Ind of aeper: ? sri 2d. Is:1:a:ed :acs of sear:up: Reactor is critical at low power.

26. Uni:s n Test S:stus (?rter :a Oc :.ercial cpers:1:n): rarecas: A: hie.fet

:- c c :T::.c: Y M/A N/A r.."..c I; ra:c: Y N/A N/A _ . _ . -

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TSP-3 Attachrant-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2

? age 1 o' 1 Do cke t ::o. 50-267 Unit Fort St. Vrain Date- Januarv 10, 1983 Co:pleted By L. M. McBride Telephone (303) 785-2224 lbnth December, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(Mh'e-Ne t ) (Mrie-Ne t) 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 n.0 23 0.0 3 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 0.0 16 nn

• Generator on line but no net generation.

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PF E M539!?"d?_ _ANp p41[R, a3.necl}ms 8"'m n '- 50-26 7. . .. . . . . .-

i,n,y u3,,e Fort St. Vrain

,,3, g January 10, 1983 au a.e ine nr L. H. McBride mEner muni December, 1982 .si isnming (303) 785-2224 i

SillfTTING InsWN SYSTFJl 0481)NEN T HO. 1) ATE 1Yl'E BAIRATlisN REAsim HEACTtHL f f.R I 0)DE GlDE CAllSE ANil DIRRErt IVI' A('TipN Tu l Nr.VI.N r Ri t:tikktJ4e:).

82-01/ 821201 F 744.0 li 3 N/A IBil INSTRU I.oop 1 shutdown followed by reactor scram and turbine-generator trip on 820930. Outage continued due to primary coolant chemistry impurities and repair of steam generator.

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- . _ _ _ _ _ _________-_-_.-.A_____._----____--______._______________.-_-.__'-___._____l___-_________-----______.-___.--._-.____________--_--_-.__.____________

REFUELING INFOPEATTCN I

_1. Name of Facility.  ! Fort St. Vrain Unit No. 1 2.

Scheduled shutdown. date for next refueling l September 1, 1983 f

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Scheduled date for restar:

follcuing refueling. November 1, 1983 4 Will refueling or resumption of operation thereafter raquire a technical specification change ,

or other license amendment? Yes

. If answer is yes, what, in l 3eneral, will these be? Use of type H-451 graphite.

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If answer is no, has tha reload fuel design and core configura-tion been reviewed by your plant i Safety Review Committee to deter-

nine whether any unreviewed ~ ~ ___

f safety questions are associated with the core reload (Reference  !

j 10CFR Section 50.59)? I I

j If no such review has taken ____ ________________

! riace, when is it scheduled?

, 5. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; supporting information. to be determined.

6. I:portant licensing considera-

, tions associated with refueling,

e.g., new or different fuel de-

, sign or supplier, unreviewed -= ------ = - --

e j design'or perfor=ance analysis '

i methods, significant changes in j i fuel design, new operating pro-  ;

cedures.

7. The nu=ber of fuel asse=blies 1482 HTGR fuel elements.

9 (a) in the core and (b) in the spent fuel storage pool. 11 spent HTGR fuel elements I

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, S. The present licensed spent fuel '

' pool seorage capacity and the Capacity is limited in size to about one-si:e et, any increase 1n licensed third of core (approximately 500 HTGR

, storage capacity that ,nas ,aeen elements). No change is planned.

g requested or is planned, in number of fuel assemblies.

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, EFUELI:G I::FOR:%TIO!i (CO::TI!UED)

9. The projected date of the 1992 under Agreenents AT(04-3)-633 and last refueling that can be DE-SC07-79ID01370 between Public Service.

discharged to the spent fuel

• Company of Colorado, General Atocic pool assuming the present l Company,andDOE.*

licensed capacity. i

• 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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