ML20070F125

Forwards Monthly Operating Rept for Oct 1982

ML20070F125
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/08/1982
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-82510, NUDOCS 8212200094
Download: ML20070F125 (2)

Text

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f 16805 WCR 19 1/2, Platteville, Colorado 80651-9298 November 8, 1982 Fort St. Vrain Unit No. 1 P-82510 Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Fort St. Vrain Nuclear Generating Station Public Ser< ice Company of Colorado Docket No. 50-267 Operating License DPR-34

Dear Sir:

Attached please find the October, 1982, Monthly Operating Information for the Fort St. Vrain Nuclear Generating Station.

Ver truly yours, l

l fi f6(b fI Don Warembourg Manager, Nuclear Production DW/lsb Attachment cc:

Mr. John T. Collins Office of MIPC 0[ e "TD N

e2122 coo 94 e211oe 0

gDRADOCK 05000267 PDR

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f MONTHLY OPERATING INFORMATION DISTRIBUTION Number of Copies 0)(Original of P Letter)

Director ------------------------------------

Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Comnission Washington, D.C.

20555 Mr. John T. Collins, Re gional Adminis trator - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 1 (P Letter)

Mr. George Kuzzycz U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20034 2 (P Letter)

Director Of fice of Management Information and Program Control U. S. Nuclear Regulatory Commission Washir.gton, D.C.

20555 Mr. Te d C in t u l a - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

U. S. Nuclear Regulatory Commission 1:105 National Maryland Bank Building Washington. D.C.

20555 Gas Coole d Reac to r As socia tes - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P I4tter)

ATTN:

Mr. R. A. Evans 3344 North Torrey Pines Court Suite 300 LaJolla California 92037 Electric P owe r Resea rch Institute - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

ATTN:

Mr. Melvin E. Lapides 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303 Mr. Richard Phelps, FSV, GA. Site Representative - - - - - - - - - - - - - --- 1 (P Letter)

General Atomic Company 16654 Weld County Road 191/2 Platteville, Colorado 80651 NRC Resident S i t e In s p e c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (? Letter) l l

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TSP-3 Attachment-D Issue 2

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50-267 ortu Truc mTA arrorr DocurT 3o.

DATE November 8, 1982 conyt,.no 3T L. M. McBride T arruost (303) 785-2224 OrERATING STATUS sons 1.

Unit same:

Fort St. Vrain 2.

Reporting Period:

821001 through 821031 3.

Licensed Thermal Power (Wt):

842 4.

Nameplate Rating (Cross We):

342 3.

Design Electrical Rating (Net We):

330 6.

Maximus Dependable Capacity (Grose We):

342 7.

Maximum tependable Capacity (Net We):

330 8.

If changes Occur in Capacity Ratings (: team Number 3 Through 7) Since Last Report, Give Reasons:

None 9.

Power Level To i."hich Restricted, If Any (Net We):

231 lo. Reasons for Restrictions, If Any:

Restriction to 70% pending resolution of contractual matters.

This Month Tear to Data cumulative

11. aours in Reporting period 745 7,296 29,257 1:. sumber of nours aeactor was critical 36.8 4,206.2 18,784.6

13. Reactor Reserve stutdown nour.

0.0 0.0 0.0

a. nours' cenerator on-t.ine 0.0 3,266.2 13,174.5

15. enic Reserve shutdown nours 0.0 0.0 0.0 16.

Gross Thermal energy Generated (:53) 150.1 1,842,635.6 6,776,580.4

17. cross siectrical toergy cenerated (Wa) 0 635,548 2,326,904 ts. set tieetrical toergy cenerated (Wa)

-3,430 578,415 2,132,674 19.

Unit Service Factor 0.0 44.8 45.0

o. ratt Availability ractor 0.0 44.8 45.0

n. tait capacit, ractor (csins noc xee) 0.0 24.0 22.1

22. tait capacity raetor (t sing cra xet) 0.0 24.0 22.1 23.

Unit Forced Outage Rate 100.0 25.8 32.2

4. Shutdowns Scheduled Over Next 6 Mo nths (Type, Date, 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. :f Shut covn at tad of Report Period, tstimated cate of scartup:

821116-0000 hours 25.

Units In Test Status (Prior to Coc::nercial Operation):

Forecast Achieved txtnn ennen:n N/A N/A Inna atenic:n N/A N/A ccmac:n cetRAn.:s N/A N/A

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s TSP-3 Attach mnt-3A Issue 2 AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unie Fort St. Vrain Date November 8. 1982 Completed By L. M. McBride Telephone (303) 785 ???4 Month October. 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL..

(MWe-Net)

(MWe-Net) 1 0.0 17 0.0 2

0.0 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 0.0 16 0.0

• Generator on line but no net generation.

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ISP-1 At t achwei t -1C Innise 2 Page 1 of I

_L', NIT SIIUTtWNS_AN_D_PWE_R_R_E_llU_C_WNS,-

i,CxET t.. __50-267 i m n^ne ___ Eor _t_St._Vrain _.._

om November 8, 1982 CoNri.cm> nT L. M. McBride

___(303)785-2224 Octob n 1982 in.rruoNE REreRT town P&:1110D OF

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FilUTTING luul SYSTEff Cett'ONENT No.

DATE TYPE DURATION REASON REACTOR II.R I CollE Q)DE CAtISE AND Q1RRI:CTIVE ACTION TO l'REVI.NT RECllRRENCE 82-014 821001 F

745.0 H

3 N/A 1 811 INSTRtl Loop 1 shutdown followed by reactor scram and turbine-generator trip (on 820930). Continued outage to

{

perfom primary and secondary i

maintenance.

REFUELING INFORMATION 1.

Name of Facility.

Fort St. Vrain Unit No. 1 2.

Scheduled date for next 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 change 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

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safety questions are associated with the core reload (Reference i

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 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool.

29 spent HTGR fuel elements.

8.

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

requested or is planned, in number of fuel asse=blies.

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REFUELING INFORMATION (CONTINUED) i 9.

The projected date of the

' 1992 under Agreements AT(04-3)-633 ar.d last refueling that can be

' DE-SC07-791D01370 between Public Service discharged to the spent fuel Company of Colorado, General Atomic pool assuming the present Company, and DOE

• licensed capacitv.

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• The 1992 estimated date is based on the understanding that spent fuel t

discharged during the e.erm 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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