ML20151V782

Monthly Operating Rept for Jul 1988 for Fort St Vrain Unit 1

ML20151V782
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/31/1988
From:	Fuller C, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808230004
Download: ML20151V782 (13)

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PUBLIC SERVICE COMPANY OF COLORADO- ,

FORT ST. VRAIN NUCLEAR GENERATING STATION

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I MONTHLY OPERATIONS REPORT i

NO. 174 July, 1988 l

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O 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 .No. OPR-34. This report includes the monthly partial ~ scram / maximum temperature reports for control rod drive and orificing assemblies.- This report is for the month of July 1988.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The turbine generator was removed from service on July 5,:1988, at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />. The reactor was manually shutdown for helium circulator bolting replacement at 2323 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.839015e-4 months <br />.

1 On July 6,1988, it was discovered that core support floor (CSF) i vent valve V-111063 was not full open as it should have been.

Further investigation identified that the valve stem of V-111063  :

had become separated from the disc. Had the CSF vent system been I isolated during rapid PCRV depressurization (Design Basis Accident No. 2, considered an incredible accident), excessive differential pressure could have developed across the CSF and resulted in deformation of the CSF casing sidewall and top head.

This event has been investi and reported to the Nuclear Regulatory Commission in Licen'seegated Event Report 89-011. i 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS ~

OF 10% OF THE ALLOWABLE ANNUAL VALUE l

None '

3.0 INDICATION OF rAILEO FUEL RESULTING FROM IRRADIATED FUEL QAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY ,

TEMPERATURE REPORT '

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OPERATING DATA REPORT DOCKET N0. '50-267' DATE August 15. 1988 COMPLETED BY F. J. Nova ~ chek .

TELEPHONE (303) 620-1007 OPERATING STATUS-NOTES

1. Unit Name: Fort St. Vrain. Unit No. 1

2. Reporting Period: -880701 throuah 880731-

3. Licensed Thennal Power (MWt): 842'

4. Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330

6. Maximum Dependable Capacity (Gross MWe): 342

7. Maximum Dependable Capacity (Net MWe): 330

8. If Changes Occur 1., Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted, If Any (Net MWe): 270.6

10. Reasons For Restrictions, If Any: Reanalysis of safe shutdown cooling following a 90 minute interruption of forced coolina. .

This Hor.th Year To Date Cumulative

11. Hours In Reporting Period 744 5.111 79.656

12. Number Of Hours Reactor Was Critical 119.4 3.798.1 37.244.8

13. Reactor Reserve Shutdown Hours 0 .D_, 0.0 3.0

14. Hours Generator On-Line 113.2 3,487.3 25.072.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thennal Energy Generated (MWH) 74,262.2 _1,954,375.5 12,887,710.1

17. Gross Electrical Energy Generated (MWH) 28,121.0 718,184.0 4,260,404.0

18. Net Electrical Energy Generated (MWH) 24.804.0 672.993.0 3,763.259.0

19. Unit Service Factur 15.2 68.2 31.5 -

20. Unit Availability Factnr 15.2 68.2 31.5

21. Unit Capacity Factor (Usi MDC Net) 10.1 1Q.4 14 1

22. Unit Capacity Factor (Using DER Net) 10.1 39.9 14.3

23. Unit Forced Outage Rate 84.S 31 A 62_1 24 Shutdowns Scheduled Over Next 6 Months (Type Cate, and Duration of Each):

Helium Circulator ReoairL_

880801. 1704 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.48372e-4 months <br />.

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: .0ctnhor 11.1QRR

26. Units In Test Status (Prior To Cocrnercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INIflAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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'AVERAGEDAILYUNITPOWERLEVEL-Docket:No. 50-267 Unit Fort St. Vrain Unit No.1 Date August 15, 1988 Completed By F. J. Novachek-Telephone (303) 620-1007 Month JULY i

-DAY AVERAGE DAILY POWER LEVEL DAY. . AVERAGE DAILY POWER LEVEL-(MWe-Net) (MWe-Net)

'l 246.3 17 0.0 2 245.8 18 0.0 3 247.1 19 0.0 4 246.8 20 0.0 5 128.7 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 i

14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

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• Genera +or on line but no net generation.

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TSP-3 Attachment TSP-3C issue 2 MNI T SHUTDOWNLAN,iD_PQWER REDUCIIONS .

.50-267

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DOCKET NO.

UNIT NAME Fort S t . V ra'i n Un i t No. 1 DATE Aucust 15. 1988 COMPLETED BY f,Eank J. Novachek MEPORT MONili- JULY. 1988 l ] I 'l I lhEiHOD Orl i l l l

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l SHUTTING l l l l CAUSE AND CORRECTIVE ACTION I no. - l DATE liveEl DURAllON I REASON lDOWN l 1. E R # ISYSIEMICOMPONENTl TO PREVENT RECURRENCE ~

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l l l~1 l l REACTOR I ICODE ICODE I I

-l l l l l I l l l I 188-121 88070S I S l 630.8 l le i N/A 'AB

-l I I I I 1 1 1 l CMP .I Reactor Manual 8y Shutdown For Scheduled - 1 I I I I I Replacement Or Halimn Ci rculator Bolts.

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Refer To LER 87-019. ~

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? I l 1. Name of Facility l Fort St. Vrain Unit No.'1 l 5 l _

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l 2. Scheduled date for next l . ,

l l refueling shutdown _". I Aprili4, 1989 l- i 1 j. 1 -' l I 3. Scheduled date for restart l May;27, 1989 l l following refueling. 'l l l l .I l4 Will refueling or resumption ~ofl No l ,

l operation thereafter require a l l l technical specification change l .I l or other license amendment? I l 1 l I -'

l If answer is yes, what, in 1 ---------------- i

.l general, will these be? l l 1 l l l If answer is no, has the reloadj / l l fuel design and-core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l .No l

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l to deter.rine whether.any unre- 1 i j viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section i l l 50.59)? I j l l 1 / I l If no such review has taken [ 1988 l l place, when is it scheduled? l l

l 1 l l 5. Sr.heduled date(s) for submit- l l l ting proposed licensing action l ---------------- l l and supporting information. 1

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l l 1 l 6. Important licensing considera- 1 l l tions associated with refuel- l l l ing, e.g., new or different l' l l fuel design or supplier, unre- 1 ---------------- l l viewed design or, performance [ j i analysis methods, significant l l l changes in fuel design, new l l l operating proceaures. l l

I I l l 7. The number of fuel assembifes l l l (a) in the core and (b) in' the l a) 1482'HTGR' fuel elements l l scent fuel storage cool. I b) U spent fuel elements l s

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't REFUELINGINFORMATION(CONTINUE _Dl 9 .

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l 8. The present licensed spent fuell l( ,

l- pool storage' capacity and the l ,

l-size of any increase in l .

l Capacity is'. limited in size to .l l licensed storage capacity that I about one-third of core l l has been requested or is, I (approximately F00 HTGR elements),1; l . planned, in number of fuel , l No change is planned., l

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I I I i l 9. The projected date of the last'l 1996 under Agreements AT(04-3)-633l l l refueling that can be dis- .. I and DE-SC07-791001370 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

l caoacity. I Company, and DOE.* l s

< 1 The 1996 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 accommodate eight fuel segments. It' ,is i estimated that the eighth teel segment will be discharged in 1996.

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I a 3..  :/f y CONTROL R0D ORIVE' PARTIAL SCRAM ~

TEST RESULTS AND MAXIMUM DAILY" .

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.lyl TEMPERATURE' REPORT- f f

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- REPORT PERIOD:

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,, JULY 1,'1988 --JULY'5,'1988-

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jp Prepared by: [/ / ,

Jane Mason e Preventive Maintenance -

q Techrif cian F 4 Systems Engineering f

Aoproved by: t- . # ,

Steve Knes. '

Preventive Maintenance.

Supervisor Systems Engineering '

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- c Public Service Company of Colorado Fort St. Vrain Unit No. 1 y . .

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l. ABSTRACT This report summarizes the partial scram test results and the maximum daily temperature of those , control rods with motor

( temperatures above~215 degrees Fahrenheit. It.is prepared to ',.

1 satisfy the Fort St. Vrain Interim Technical Specification Surveillance Requirement 4.1.1.A.1.a. The time period covered by this report is July 1,1988, through July 5,1988.

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e II. BACKGROUND Because proper operation.oftheControlRbdDriveMechanism (CRDM) is. critical for safe operation of the reactor, a~ series of qualification tests .were conducted over a one year time span to demonstrate its capability. The motor . temperature during these tests varied between 200 degrees Fahrenheit and 230, degrees Fahrenheit, and averaged 215 degrees -Fahrenheit.

A total of 130,000 jog cycles'plus 1600 scrams was logged during the final design testing, which is many times that expected .over the normal life of a CROM. The operating temperature of the CRDM is limited by the_ motor's Class H insulation which is de-rated to 272 degrees Fahrenheit to account for motor temperature rise, . frictional torque increase,i:nd winding life expectancy.

• In order io monitor CRDM temperatures, Resistance Temperature Devices (R' T s) are mounted on the closure plate, orifice valve motte plate, and CRDM motor as shown on Figure 1. 'All CRDM's inst illed in the Reactor are equipped with .RTO's.

-Three reco"ders located in the control room record each of.

these temperatures for all 37 CRDM's. CRDM motor temperatures are alarmed at 212 degrees Fahrenheit and 247 degrees Fahrenheit.

CRDM motor temoerature are monitored at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that they are less than 250 degrees Fahrenheit, which is a limiting condition _for operation. If one or more CRDM motor temperature (s) is found to be greater than 215 degrees Fahrenheit during the daily surveillance, the motor temperature of all CRDMs exceeding 215 degrees Fahrenheit is recorded and a partial scram test is performed on the CRDM with the highest motor temperature .once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. These surveillances ensure that CRDM motor temperatures exceeding 215 degrees Fahrenheit do not degrade the CRDM's reliability to perform its design function when required. ,

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III.

SUMMARY

OF RESULTS '

Regions 12 and 30 CRDM motor temperatures exceeded 215 degrees Fahrenheit from July 1 through July 5,1988.

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The partial scram test results and maximum daily temperature of those CRDMs with motor temperatures above 215 degrees j Fahrenheit are presented on Table 1. The pertinent parameters-l are: reactor region involved, control rod -position, maximum daily motor . temperature, extrapolated scram times (surveillance value and. Back EMF calculated value) and starting acceleration. The-control rod position is presanted

.because of its relationship to available starting torque which affects the starting acceleration and extrapolated scram time calculated by surveillance. The surveillance extrapolated scram time is affected by control rod position because it-is calculated using distance travelled versus time. Since- the acceleration is slower- at lower control rod positions, a longer periori of time is required to reach. steady state speed.

This longer acceleration period results in a decrease in distance eravelled over a given period of time, thereby indicating a longer extrapolated scram time. The extrapolated scram time calculated' by the Back EMF. program applies a correction factor to provide a projected full length scram time. Therefore, the surveillance scram times can only be comoared for trends if the control rod position is approximately the same. The Back EMF calculated scram time.is more readily trended since the value should be independent of control rod position.

The starting acceleration values presented are calculated by the Back EMF program. These values reflect the CRDM's freedom of rotation to accelerate to steady state speed and therefore are considered to be valuable performance indicators. Two values are presented: The actual acceleration measured during a scram from the indicated control rod position and- the projected acceleration if the control rods were at the full  !

out position (qreater than 188 inches). If the control rod l position is greater than 188 inches, no data is presented for 1 a projected starting acceleration since the actual and

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projected are the same. ~As indicated with scram times, the projected starting acceleration is more readily trended since l the value should be incependent of control rod position. l IV. CONCLUSIONS l j

9 The performance of CRCMs with motor emperatures in excess of l

215 degrees Fahrenheit did not show any significant trends or  ;

oegradation during this report period. Therefore, it is concluded that CRDM motor temperatures exceeding 215 degrees Fahrenheit did not degrade the CRDM's capability to perform its design functioa wnen required.

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h Public Service ~  :=t h 16805 WCR 19 1/2, Platteville, Colorado -80651 August 15, 1988 Fort St. Vrain.

Unit No. 1 P-88301 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

JULY 1988 MONTHLY OPERnTIONS REPORT

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of July 1988, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

If you have any questions, please contact Mr. M. H.-Holmes at (303) 480-6960.

Sincerely, c.g .Ch b bl C. H. Fuller 3

Manager, Nuclear Production

Enclosure cc

Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain q

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