ML20027E740

Monthly Operating Rept for Oct 1982.Narrative Summary Encl

ML20027E740
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/08/1982
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20027E736	List: ML20027E735 ML20027E740
References
NUDOCS 8211150670
Download: ML20027E740 (8)

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

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MONTHLY OPERATIONS REPORT NO. 105 October, 1982 I

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'~~8211150670 821'1 l'O ~

-'s) . PDR ADOCK 05000267 A R PDR i

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j This report contains the highl'ights 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 October, 1982.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The reactor has been shut down for the entire month of October as the result of a reactor scram, loop shutdown, and moisture ingress which occurred on September 30. '

Necessarymaintena[iceandsurveillanceshavebeencompleted which will allow operation through March 1, 1983, after the moisture has been removed. At months end, the top priority is moisture removal utilizing the purification trains.

1.2 Operations At the beginning of the month, the plant was in a shutdown condition as a result of the reactor scram that occurred on September 30, 1982. Indications of a moisture ingress during the said transient were under investigation.

) To the advantage of the shutdown condition, all departments were mobilized to make required repairs and perform all surveillance tests deemed necessary to allow for operation through March 1, 1983. All tests and repairs were completed satisfactorily by October 2, but following the performance of the semi-annual " Loss of Outside Power and Turbine Trip" surveillance test, problems in the Plant ,

Protective System caused several "A" circulator accumulator '

firings and hence additional moisture ingress.

The reactor was brought critical on October 2, but when power was increased on October 3, high moisture levels caused a reactor scram, a loop 1 shutdown, and steam / water dump. This made it apparent that both helium purification trains would be required to remove all of the moisture, and since HV-2301 had not been operating properly, a decision to depressurize the prestressed concrete reactor vessel was made so that the valve could be repaired.

HV-2301 was removed for seat repair and a temporary seal was installed to allow regeneration of the "A" train, but when this was attempted on October 13, the seal failed and leaked radioactive helium to the Reactor Building. An 3 unusual event was declared when the stack monitor l 3 indications moved slightly upscale, and normal access to

]  : the Reactor Building was restricted for several hours.

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) While the reactor was at refueling condition, it was prudent to remove the reserve shutdown material from l Region 27. When the new control rod drive was tested following installation in the prestressed concrete reactor.

vessel, it was found that the rod position transducers did not work and the rod had to ba pulled again. Difficulties were experienced in withdrawing the rods completely into the auxiliary transfer cask. This was finally accomplished using the manual retract tool on October 24.

The condenser was removed from service on October 24 to .

replace the main steam desuperheater drain lines where they enter the condenser. -

All major work was completed, and feedwater was supplied to the steam generators on October 28. -

The reactor was brought to critical on October 29, but the high level of moisture prevented the addition of heat to the core. The helium transfer compressor was placed in service to maximize flow through the purification train.

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 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached e

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O Attachamat-3B Esau. 2 50-267 or m Ttsc a TA Rzroar Docxrr so.

DATE November 8, 1982 court.r::D sT L. M. McBride trz.zemose (303) 785-2224 OPERATING STAT 05 mo:ss

1. cart s : Fort St. Vrain-

2. naparting recto 4: 821001 throuah 821031

3. Licensed Therasi rower () Sit): 842

4. Nam. place Racing (Gross W e): 342

5. Design Electrical Racing Ofet We): 330 .

6. Mav4== Dependable Capacity (Gross We): 342

7. Maximse :ependable capacity (3et We): 330 m

8. If changes occur in Capacity Ratings (Items Number 3 Through 7) Since tast Report, Give Reasons:

None

9. Power Lavel To Which Restricted. If Any (Net We): 231 lo. Reasons for Restrictions, If Any: Restriction to 70% oending resolution of contractual matters.

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This Month Taar to Data cumulative i 11. aours in a porting perio4 745 7,296 29,257

12. wumber of sours aeactor vu critical 36.8 4,206.2 18,784.6

u. auctor r. serve shutdown sours 0.0 0.0 0.0

15. sours'cenerator on-t.in. 0.0 3.266.2 13,174.5

15. enit anerve shutdown sours 0.0 0.0 0.0

16. cross ner_al energy c.n. rat.4 csis) 150.1 1,842,635.6 6.776,580.4

17. crou nectrical snarar .neracea c ones) 0 635,548 2,326,904

18. set n.ccrical energy cen. rat.4 (>sar) -3,430 578,415 2,132,674

19. cnit Servic. ractor 0.0 44.8 45.0

o. cast Availability ractor 0.0 44.8 45.0

1. enit capacit- ractor (cains .-2x: see) 0.0 24.0 22.1

. suit capacity ractor (cains att set) 0.0 24.0 22.1

23. cnit rare.4 oucase aat. 100.0 25.8 32.2

24. Shutdevns Scheduled over Nart 6 Months (Type, cat , and Duration of Each): Plant recovery operations-821101 thru 821115-360 hours; Surveillance Testing-830301 thru 830331-744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

5. If shut :own at rad of a.oere period, :sti=at.4 cat. of startup: **d21116-0000 hours

5. cnits :n Test Status (Prior to Co:=ercial operation): rorecast Acnieved In nat :n n:A:.= N/A N/A Inn.u. ru=ncm N/A N/A

mzac:A:. cetza ::3 N/A N/A o*821116 date reflects infonnation is of October 31, im.

TSP-3 Atttchment-3A AVERAGE DAILY UNIT POWER LEVEL 1ssue 2 Page 1 of 1 Docket No. 50-267 Unic Fort St. Vrain Date November 8', 1982 Complaced By L. M. McBride Telephone (303) 785 ???4 Month Octobar. 1982 DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL..

(We-Ne t) (We-Net) 1 0.0 -17 0.0 2 O_0 18 0.0 3 0.0 19 O_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 O_0 16 0.0 l

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• Generator on line but no net generation.

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At I m ilsm es t-1C Iqmise 2 ror i ..r i

-LWIT SilUitNWit_S_AN_D__P_tWE_R__R_E_l_iU_C_R_m.s 1**nEr rai. __._50. _- 2_6 7_ . _ _ .

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. IINIT f4AttE fQ r,( ,$,t_,,,y{3 jn _ , _,

natE November 8, 1982_

Corri.Ern> nr _ L. M. McBrid_e .

REroRr mWni ctober_,_1982_ m.EnRmE __(30_3)785-2224 HET110D OF SillrITING IMWN SYSTDI C0tFUNENT 10 0 . DATE ITFE lANtATION REASON REACTOR I.ER I OlDE GIDE CAUSE AND CORPICTIVE ACTION TO l'REVI.NT Rf'.CURRDat:E 82-014 821001 F 745.0 11 3 N/A IBil INSTRU Loop 1 shutdown followed by reactor scram and turbine-generator trip (on 820930). Continued outage to perfonn primary and secondary maintenance.

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q REFUELING INFORMATION

1. Name of Facility. _

Fort St. Vrain Unit No. 1

2. Scheduled date for nexc refueling shutdown. July 1. 1983

3. Scheduled date for restart following refueling. August 1, 1983

4. Will refueling or resumption of .

operation thereafter require a ,

technical specification chansk or other license amendment? Yes -

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

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter- .

mine whether any unreviewed safety questions are associated with the core reload (Reference 10CFR Section 50.59)?

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If no such review has taken _

place, 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. Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed -- --

design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies 1482 HIGR fuel elements.

(a) in the core and '(b) in the spent fuel storage pool. 29 spent HIGR fuel elements.

8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-si:e of any tacrease in licensed storage capacity that has been third of core (approximately 500 HTGR elements). No change is planned.

requested or is planned, in nu=ber of fuel assemblies.

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LMING INFORMATION (CONTINUED) i

9. The projected date of the  : 1992 under Agreements 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 Atomic pool assuming the present Company, and DOE.*

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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