ML20080M607

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Monthly Operating Rept for Jan 1984
ML20080M607
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 01/31/1984
From: Fuller C, Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84048, NUDOCS 8402210197
Download: ML20080M607 (10)
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l PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION 1

C MONTHLY OPERATIONS REPORT NO. 120 January, 1984 o

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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 the month of January, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND AAJOR SAFETY RELATED MAINTENANCE The month of January was highlignted by pre-shutdown activities, shutdown, and plant reconfiguration for shutdown activities.

The plant operated near 70% power for the first two weeks, except for six hours when the turbine was tripped due to amplidyne problems. The reactor power was reduced to 50%, due to leakage problems on "1A" circulator inlet piping.

On January 17, the power was reduced to 30% to allow going to the " low power" position. Pre-shutdown surveillances were then completed, and on January 19th, the turbine generator was manually tripped. Core Support Floor testing was then performed while decreasing power. The reactor was manually scrammed on January 20, 1984, but decay heat removal requirements delayed complete cora depressurization until January 26, 1984.

Prior to refueling, the helium purification inlet valves and the

/^ '_ "B" train cooler were removed, and the electrical bus work was

\: started. Essentia'i Gus I has been removed from service, and is being upgraded at this time. Shutdown work included the deaerator and condenser inspection, instrument calibrations, loop 1 valve work, IA circulator piping removal, moisture

. monitor work, and removal of the low pressure rotor on the turbine generator.

All work is progressing, but asbestos insulation removal delays have slowed progress. Refueling is delayed due to electrical cable conductor problems in the Fuel Handling Machine cable network.

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2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10'40F THE ALLOWABLE ANNUAL VALU_E 1.an e 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached F

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  • '* TSP-3 Attschmen t-38 Issue 2 OPERAUNC DATA REPORT DOCKET No. 50-267 DATE February 6, 1984 CoxP:.ETED BY Chuck Fuller TELEPHONE (303)785-2224 OPERATING STATUS sons
1. Unit Name: Fort St. Vrain

.2. Reporting Period: 840101 thru 840131

- 3. - Licensed Thermal Power OSit): - 842

4. l Nameplate Rating (Cross We): 342

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5. Design Electrical Rating (Net We): 330
6. ~Nazimum Dependable Capacity-(Gross We): 342
7. Maximus Dependable Capacity (Net We): 330 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

-None

9. Power Level To Which Restricted, !! Any (Net We): 231

'10. Re'asons for Restrictions, If Any: Restriction to 70% pending resolution of contractual matters.

This Month Year to Date Cumulative

11. Hours in Reporting Period 744.0 744.0 40,225.0 -
12. Number of nours Reactor was critical 468.0 468.0 26,295.3 1h Reactor Reserve Shutdown Hours 0.G ___

0.0 0.0 ,

'14. aours cenarator on-Line _,

446.6- 446.6

  • 18,249.8
15. I' nit Reserve Shutdown Hours 0.0' O.0 0.0
15. cross The. mal Energy Generated (Wu) 240,318.8 240,818.8 9,762,136.4
1. : crose Electrical snergy cenerated (W uy 77,412 77,412 3,230.862

- 18. Ne't Electrical Energy Generated (WR) 71,302 71.302 2.942,832

19. Unit Service Factor 60.0 60.0 45.4
20. Unic Availability Factor 60.0 60.0 45.4
21. . Unit Capacity Factor (Using MDC Net) 29.0 29.0 22.2
22. Unit Capacity Factor (Using DER Nee) 29.0 29.0 22.2
23. Unit Forced Outaga Rate 40.0 40.0 39.9
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Zach): Refueling 2-1-84

-through 4-18-84, at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, 1869.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

23. If shut Down at End of Report Period. Estimated Date of Startup: 4-19-84 f' 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INIMAL CRIUCALIn N/A N/A

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INIHAL ELECTRICIn N/A N/A comCut OPERATION N/A N/A

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. . TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date Februarv 6. 1984 Completed By Chuck Fuller Telephone (303)785-2224 Month January 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL.

(MWe-Net) (MWe-Net)

.1 180.0 17 138.5 2 180.1 18 62.3 3 180.3 19 49.9 4 178.2 20 0.0 5 176.7 21 0.0 6 176.5' 22 0.0 7 176.3 23 '0.0 8 176.3 24 0.0 9 177.4 25 0.0 10 102.0 26 0.0 e .

11 176.6 27 0.0

12. 177.4 28 0.0 13, 176.7 29 0.0 14 176.2 30 0.0 15 176.0 31 0.0 16 176.0
  • Generator on line but no net generation.

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Page 1 of I' UNIT SNUTDIANIS AND r(arER RE1p>CTUNS

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noCxET m. 50-267 , .,,

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, Unit Nun! ' Fort St. Vrain nATE February 6, 1984 ..

Conrirrm ut Chuck Fuller REroRT n0Nm January 1984 tci.ErmmE (303)785-2224 METHOD OF

, SHUTTINC DonNt ST9TF.H CODFONFNT NO. DATE TYRE DURATION REASON REACTOR I.ER I CODE _0)PE CAUSE AND 0)RRECTIVE ACTION 70 rREVENT RECITRRENCE 84- -

840110 F 6.9 A 4 N/A EL MG Turbine generator trip caused by amplidyne failure. Reactor-remained critical'.

- 84-002 840119 S 290.5 C 2 N/A ZZZ ZZZZZZ Refueling.

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REFUELING INFORMATION I l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l l 2. Scheduled date for next l 3rd Refueling: l 4th Refueling:l l refueling shutdown. I currently underwayl Feb. 1, 1986 l l l l l l 3. Scheduled date for restart l April 18,1984, l May 1, 1986 l l following refueling. I 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> l l l l l l l 4. Will refueling or resumption ofl l l

.l operation thereafter require a l Yes l None Expected l l technical specification change l l l l or other license at:'.endment? l l - l l l l l

! If answer is yes, what, in l Use of type H-451 l ----------- l l general, will these be? l graphite. l l l l- l l l If answer is no, has the reload] l l l fuel design and core configura-l l l l tion been reviewed by your l l l l Plant Safety Review Committee l ---------------- l No l l to determine whether any unre- l l l l viewed safety questions are l l l l . associated with the core reloadj l l l (Reference 10 CFR Section l l l l 50.59)? i l l

l. I I I l If no such review has taken l ---------------- l 1985 l l place, when is it scheduled? I l l l l l l l 5. Scheduled date(s) for submit- l Submitted to NRC l l l ting proposed licensing action l December 2,1983. l ------------ l l and supporting information. l l l l l l l l 6. Important licensing considera- l l l l tions associated with refuel- l l l l '

ing, e.g., new or different l l l l fuel design or supplier, unre- l ---------------- l ------------ l l viewed design or performance l l l l analysis methods, significant l l l

-l . changes in fuel design, new l l l

-l operating procedures. I I l l l l l .7. The number of fuel assemblies l l l (a) in the core and (b) in the l 1482 HTGR fuel elements. l l spent fuel storage pool. l 11 Spent HTGR fuel elements. l

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REFUELING INFORMATION (CONTINUED) l .

l l l 8. The present licensed spent fuell l l- pool storage capacity and the l .

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l. size of any increase in l Capacity is limited in size to l l . licensed storage capacity that l about one-third of core l l has been requested or is l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. l l l l l 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. I Company, and DOE.* l
  • . 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 'lant. '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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Public Service Company Cf Odlendo a

16805 WCR 19 1/2, Platteville, Colorado 80651 February 13, 1984 Fort St. Vrain Unit #1 P-84048 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

REFERENCE:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of January, 1984.

Very truly yours, WA Don Warembourg

> Manager, Nuclear Production Enclosure cc: Mr. John T. Collins

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MONTHLY OPERATIONS REPORT DISTRIBUTION i NUPBER OF COPIES l

and Enforcement - - - - - - - - - - - - - - - - - - - + , b12( riginal of P Letter)

- ATTN:

OfficeDocument of Inspection Control Desk i U. S. Nuclear Regulatory Commission Washington. D.C. 20556 Mr. John T.' Collins. Regional Administrator - - - - - . - - , - - - - , - - - - - - 1 (P Letter)

Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington. TX 76011 Mr. Philip C. Wagner. Project Manager - - - - - - , - - , , - - - - , - , - , , - - 1 LP Letterl

' Region IV Nuclear Regulatory Comunission 611 Ryan Plaza Jrive Suite 1000

-Arlington. TX 76011 J Depa rtment Of Ene rgy - - - - - - - - , - - - - , , - , . , , , , , . , - - , , - , 1 (_P Letter).

Technica1'Information Center P. O Box 62 -

Oak Ridge. Tennessee 37830 Col o ra do Depa rtment O f He a l th - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

ATTN: Mr. Al Hazel 4210 East lith. Avenue Denver. CO 80220

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Gas - Cooled Reactor Ass ocia tes - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

ATTN: Mr. Merwin L. Brown. Ph.D.

10240 Sorrento Valley Road-Suite 300 San Diego CA 92121-1605 Electric power Research Ins titute - - - - - - - - - - - - - - - - - - - - - - , - - 1 (P Letter)

ATTN: Mr. Melvin E. Lapides 3412 Hillview Avenue P. O. Box 10412 Palo Alto. CA 94303 I NPO R > co rds Cen te r - - s - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Suite 1500 1100 Circle 75 Parkway _

' Atlanta GA 30339 Mr. Mi ke Do l pn i n - - - - - - - - - - - - - - - - - - - - - - - - - - - - , - - - - 1 ( P Lette r)

FSV. GA T Jinologies.-Inc. Site Representative GA Technclogies. Inc.

16864 Weld County Road 19 I/2 Platteville. CO. 80651 NRC Res i dent Si te Ins pector - - - - - - - - - - - - - - - - - - , , - - - - - , - - 1 (P Letter)

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