ML20245L583

Monthly Operating Rept for Jul 1989 for Fort St Vrain Nuclear Generating Station

ML20245L583
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1989
From:	Block M PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20245L573	List: ML20245L569 ML20245L583 ML20245L586
References
NUDOCS 8908220169
Download: ML20245L583 (9)

Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 186 July, 1989 l

l 8908220169 PDR- ADOCK 8907Zy'7 0500026 l- R PDC

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This: report :contains the highlights of the Fcrt'St. Vrain, Unit'

.No. 1,._a:tivities operated: under the provisions of .the. Nuclear Regulatory. Commission Operating. License No. 0PR-34. This report

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' includes the. monthly partial scram / maximum' temperature reports for

g control rod' drive and orificing assemblies. This report is forLthe month of July, 1989.

1.0 NARRATIVE,

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY p RELATED MAINTENANCE p

Tis reactor remained critical the :-ntire month'of July,1989.

On- July. 1, 1989, at 0444 hours0.00514 days <br />0.123 hours <br />7.34127e-4 weeks <br />1.68942e-4 months <br />, the turbine generator was manually tripped due to a load swinging problem. The reactor and turbine were stabilized and the . problem was corrected. The turbine generator was again placed on line at 1114 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23877e-4 months <br /> the same

. day. The turbine generator remained on line the restaof the month of July.

On. July 6, 1989, Bypass Ratio Controller Valve PV-2243 went to a, full open position, resulting in Loop I helium circulators to drop in speed. Reactor . power and turbine generator load were reduced to stabilize reheat temperature. The situation -was corrected and the reactor was returned to power and the turbine generator load was increased.

Reactor _ building .HVAC systems were a priority work item this month due.to the very high outside ambient temperatures that were beirg experienced. Maintenance continued throughout the month.

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-On ' July- 10, 1989, the hydraulic operator oil leak on valve HV-2224 resumed. On July 24, 1989, the valve was' repaired -and tested successfully.

On July 25, 1989, the engine driven firewater pump was removed from service for a minor leak repair. This is a 24-hour grace period item for LC0 4.2.6. The firewater pump was returned to service on July 26, 1989.

Toward the end of the month adjustments of core orifice valve

' positions were performed to accommodate partial insertion of contrsi rods in high power regions.

Construction w?s completed on the Security Diesel Generator.

Functional testing is in progress. Several maintenance items were successfully completed on the ACM and Emergency Diesel Generators.

Fort St. Vrain also achieved 5,000,000 production hours without a disabling injury in July,1939.

o major problems occurred during this month, thus making July 1989, the highest production month ih the nittory of Fort St.

Vrain. The net generation for July 3989, was 178,221 MWe.

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-g-210 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None L.

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fh'j 3.0 INDICATION '0F FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL ROD ORIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT Attached

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REFUELING INFORMATION L

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l l Fort St. Vrain Unit No. 1

' l 1. Na'ne of Facility l

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- l 2. Scheduled dateifor next . l None, no further refueling at- l i l refueling shutdown. - l FSV is expected. l l l l

. Scheduled date for restart: j.N/A l-ll' 3. ~ following refueling. I _ l ~

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l.4. :Will refueling or. resumption ofl N/A l l' . operation thereafter require a l l ll technical specification change l l ,

-l or other license amendment? I l.  !

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l If answer is yes, what, .in l ---------------- l  ;

l: general, will these be? I l

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l Ifianswer:is no, has the reload l l I - fuel design and core configura-l l l . tion been. reviewed by your l l. l Plant Safety Review Committee l N/A

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l to determine whether any unre-'l .l l viewed safety questions are l_ l l l- associated with the core reloadj l 1

.l (Reference 10 CFR Section l l .i

.l ' 50.59)? l l l

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, I 1 .i If no such review has.taken-

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1 l N/A l l~ ._ place,-when is it scheduled? l- l l .. . . .

1 i l 5. . Scheduled date(s) for submit- l l ,

l ting _ proposed licensing action-l ---------------- l-  !

l - and supporting information. l l  ;

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'..l 6. Important licensing'considera- l l j _- - tions. associated with refuel- l l j l ~ ing, e g., new or different . l l-l . fuel de si gn or suppli er, .unre- l ---------------- l jl

'l viewed-design or' performance l l ,

l analysis methods, significant l l -1 l changes in fuel design, new l l 1 l ' operating procedures. l l 1 . .

l l l ' 7. The number of fuel assemblies l l l l (a) in' the _ core and (b) in the l a) 1482 HTGR fuel elements l l l spent fuel storage pool. I b) 0 spent fuel elements l l l

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REFUELING INFORMATION (CONTINUED)

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l l l 8. .The present licensed. spent fuell I

l. pool storage capacity and the l l l- size of any increase in l Capacity is liruited in size to l l -licensed storage capacity that l about one-third of core l l- has been requested or is I (approximately 500 HTGR elements).]

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 No further refueling is l l refueling that can be dis- . l anticipated at Fort St. Vrain.

• l l charged to the spent fuel pool l l l assuming the present licensed l j l ~ capacity. l l Under Agreements _AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado, General Atomic Company, and DOE, spent fuel discharged during the defueling process will be stored by 00E at the Idaho Chemical Processing Plant. The storage capacity is presently sized to accommodate eight fuel segments. It is estimated

.that the' eighth fuel segment will be discharged in 1992. Discussions concerning the disposition of ninth fuel segment are in progress with DOE.

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