ML20031A081

Monthly Operating Rept for Aug 1981

ML20031A081
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/01/1981
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20031A079	List: ML20031A078 ML20031A081
References
NUDOCS 8109180379
Download: ML20031A081 (5)

Text

{{#Wiki_filter:_._ CPERATING DATA RIPORT DOCKET NO. 50-267 DATE 810901 CCMPLETED BY L. M. McBride TELEPsoNE (303) 785-2224 OPERATING STATUS NOTES a 1.

nit Name:

Fort St. Vrain 2. Reporting Period: 810801 through 810831 3. Licensed Thermal Power Otit): 842 a. Nameplate Rating (Gross We): 342 5. Design Electrical Rating Olet We): 330 N 6. Maxinass Dependable Capacity (Gross We): 342 7. Maximus Dependable Capacity (Net We): 330 6. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: None 9. Power Level To Which Restricted, If Any (Net We): 231 10. Reasons for Restrictions, If Any: NRC restriction 70% oendin2 resolution of temoerature fluctuations. This Month Tear to Data Cumulative 11. ours in Raporting Period 744 5.831 19.032 12. sumber of nours Reactor was Critical 717.9 3,774.6 12,909.8 u. Reactor Raserve Shutdown aours 0.0 0.0 0.0 14.

a.ours Generator on-Line 61". 9 2,873.4 8,566.7 u.

enic Reserve Shutdown sours 0.0 0.0 0.0 16. Gross Thermal Energy Generated (MM) 330,206.3 1,489,621.2 4,197.714.0 17. Gross Electrical Energy Generated (WH) 122,803 539,691 1,411,435 18. Net nectrical Energy Generated (WE) 120,753 494.230 1.293.531 19. Unit Service Factor 82.2% 49.3% 4 5. 0*; 20. Unn Availability rsetor 82.2% 49.3% 45.0% 21. Unit Capacity Factor (Using MDC Net) 49.2% 25.75 20.6% 22. Unit Capacity lactor (Using DER Nee) 49.2% 25.7% 20.6% 23. Unit Forced Outage Rate 17.S* 32.6% 35.95 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): hintenance/ j modification shutdown. October 15. 1981. Chronch Anunrv. 1082. { 25. If Shut Down at End of Report Period, Estirsted Date of Startup: l 26. Units in Test Status (Prior to Comercial Operation): Torecast Achieved INITIAL CRIU CAL m N/A N/A 9109100379 810909 PDR ADOCK 05000267 c:hMERC:AL OPERATION N/A N/A

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UNIT SilUTikiWNS AND POWER REldjC10NS ~ IUCKET m). 50-267 UNIT NAME Fort St. Vrain DATE 810901 i CoHPE2Tra ET I.. M. McBride REPORT HONTil Ativiis LJM_ TELEPil0NE (303) 785-2224 HE1110D OF SHUTTING DOWN SYSTEH COMPONENT N0 DATE TYPE DilRATION 'EASIN REACTOR IIR f CODE (1)DE CAUSE AND CORRECTIVE ACTION TO PREVENT llECURRINCE 81-20 810826 F 26.3 11 3 Turbine trip and reactor scram on two loop trouble while manually shutting a down IA helium circulator for i i maintenance. ] 77.8 D N/A Minor construction fire resulted in damage to several cables in cable tray and subsequent cable repair. Service of cables was not lost. 28.0 lt II/A N/A N/A N/A Commenced raise to power af ter cable repairs completed. l I. a 4 I Sunuuary: Plan to operate at 70% power for the reinainder of September, 2981. Will do testing above 70% during the first two weeks in October, 1981. j 1 1

~- d AVERAGE DAILY UNIT POWER LEVEL i Docket No. 50-267 Unit Fort St. Vrain Date 810901 Completed By L. M. McB ri de telephone (303) 785-2224 Month August, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MRe-Ne t) 1 78.92 17 216.38 2 110.88 18 213.21 3 150.06 19 219.83 4 159.25 20 220.13 5 195.46 21 220.63 6 218.63 22 220.13 7 219.58 23 220.42 I i 8 220.17 24 225.0 9 219.29 25 226.67 10 224.71 26 107.29 l 11 197.75 27 0.0 l 12 115.00 28 0.0 13 176.73 29 0.0 14 90s.ca 30 0.0 15 223.38 31 0.0 16 221.67

• Generator on line but no ' net generation,

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j REFUEE.ING INFORMATION 1. Name of Facilitv. Fort St. Vrain Unit No. 1 2. Scheduled date for next refueling shutdown. October 1, 1982 3. Scheduled date for restart following refueling. December 1. 1082 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No If answer is yes, what, in general, will these be? If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Saf ety Review Cot:mittee to deter-sine whether any unreviewed safety questions are associated The Plant Operations Review Committee will with the core reload (Reference review any questions associated with the 10CFR Section 50.39)? reload. I' no such review has taken

o. ace, when is it scheduled?

May 1, 1982 5. Scheduled date(s) for submitting proposed licensing actior and sucoorting information. 6. Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed dt.mgn or performance analysis methods, significant changes in fuel design, new operating pro-cedures, 7. The number of fuel assemblies 1482 HTGR fuel alements (a) in the core. and (b) in the spent fuel storage cool. spent 'nM fuel elements 3. The present licensed spent fuel pool storage capacity and the Capacity is 11mited in size to about one-size of any increase in licensed third of core (approximately 500 HTGR storage capacity that has been ele =ents). No chano is planned. requested or is planned, in number of fuel assemblies.

i t RE?UIT.EE ETFCitMAl".ON (CC:n.;mr A 9. De projected date of the 1986 under the Three Parc7 Agreement (Con-lasc refueli=g -Jan can be

ace AI (04-3)-633) bec men DOE,, Public A* *haeged. :s :he spenn fuel Sarrice Company of Colorado (?Sco), and pool assuming the present General Atomic Company.*

licensed cacac1:r.

• The 1986 date is based on :he understanding :hac spene fuel disc.Wged during the cer:a of the 2:ree Party Agreement vill be shipped :s the Idaho 'Jacional Engineering Laboraccry for storage by DOE ac the Idaho Chemic=1 Processing Planc (IC??). The storage capacity has evidently been sized to accomodate fuel which is expeccad :o be discharged during the eigh: year period covered by the nroe Parry Agreemanc.

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