ML20196C067

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for May l988 for Fort St Vrain Nuclear Generating Station
ML20196C067
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 05/31/1988
From: Novachek F
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20196C073 List:
References
NUDOCS 8807010003
Download: ML20196C067 (8)
v • d • e


Text

. - . ,

\

i PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION b

MONTHLY OPERATIONS REPORT I

NO. 372 l

l May, 1988 l

l i

( E O

. 8807010003BBC4$p67 ADOCK 05000,.

PDR R PDR,3

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 Nu. 00R-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 May, 1988, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On May 6, 1988, at 1234 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.69537e-4 months <br />, a reactor scram on high hot reheat steam temperature occurred following a trip of "B" helium circulator. The cause of this event was a malfunction of an anang averaging instrument in the overall plant control system.

During the transient, problems were experienced with the purified helium system which allowed small quantities of radioactive primary coolant to enter the normally non-radioactive buffer helium and bearing water systems. This eventually resulted in an unplanned, monitored release of approximately 3,600 microcuries of radioactive noble gas through the reactor building exhaust stack. This event has been investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 88-009.

On May 9, 1988, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, and again on May 10, at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />, reactor scram actuations occurred during calibration and surveillance testing of the Hant Protective System (PPS)-

circuitry. These scram actuations occurred as a result of l electrical noise induction in the nuclear instrument channels I

concurrent with PPS testing. These events will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 88-010.

The reacter was taken critical on May 18, 1938, at 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br />.

l Reactor power was maintained at less than 10 percent for primary i coolant cleanup until May 24. The turbine generator was returned l

to service en May 26, at 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br />.

l l 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS l 0,F 10% OF THE ALLOWABLE ANNUAL VALUE None l

L

! 2 g -

-s. - -- - e

, ., ~. -.. _

.g.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL' EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL ROD DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT Attache'd f

n 4

C

l

)

, a-OPERAT!NG DATA REPORT .00CKET No. 50-267

-DATE June 15. 1988 COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 l OPERATING STATUS

1. Unit Name: Fort St. Vrain. Unit No. 1
2. f.' porting Period: 880501 throgoh 880531

.3. 1.wensed Thermal Power (MWt): 842 4 .' hameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net NWe): 330
6. Maximum Dependable Capacity (Gross MWe): 342
7. MaximumDependableCapacity(NetMWe): 330
8. If Changes Occur in Capacity Ratings (!tems Numoer 3 Through 7' Sint.e5ast Report, Give Rersons:

None

9. Power Level To Khich Restricted, If Any (Net MWe): 270.6
10. Reasons For Restrictions, If Any: Reanalvsis of safe shutdown cooling following a 90 minute

_ interruotion of forced coolina.

This Mcnth Year To Date Cumulative

11. Hours In Reporting Period 744 3.647 7R.109 l' 12. Number Of Hours Reactor Was Critical 466.0 2.958.7 36.405.4
13. Reactor Rese.'ve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 260.0 2.654.1 24.239.6
15. Unit Reserve Shutdown Hours 0 . Q_ _ 0.0 0.0 l 16. Gross Thermal Energy Generated (MWH) 162.073.5 1.421.969.8 12.355.304.4
17. Gross Electrical Energy Generated (MWH) 55.048.0 513.809.0 _ 4.C36.029.0
18. Net Electrical Energy Gene.'ated (MWH) 49.844.0 480.490.0__ 3.570.756.0
19. Unit Service Factor 34.9 72.8 __

31.0 i 20. Unit Availability factor 34.9 72.8 31.0

( 21. Unit Capacity Factor (Using MDC Net) 20.3 39.9 13 R l 22. Unit Capacity Factor (Using DER Net) 20.3 39.9 13.8

23. Unit Forced Outage Rate 65.1 27.2 62.5 l 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Helium Circulator Renairs.

I 880705. 2.184 hours0.00213 days <br />0.0511 hours <br />3.042328e-4 weeks <br />7.0012e-5 months <br />

25. If 9 t Down At End Of Report Period, Estimated Date Of Startup: N/A i

Forecast Achieved

26. Units In Test Status (Prior To Commercial Operation):

I INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A  ;

I I

i i

- , - , - , , -, - -e,. - - - - , - - , , ,

~

- AVERAGE DATLY UNIT ' POWER- LEVEL .

Docket No. 50-267 Unit Fort St. Vrain Unit No.1 Date June 15, 1988 Completed By F. J. Novachek Telephone (303) 620-1007 l Month MAY l

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) l 1 251.0 17 - _ 0.0 2 251.5 18 0.0 3 249.5 19 0.0

. 4 255.6 20 0.0 5 _

246.0 21 0.0 6 126.4 22 0.0 7 0.0 23 0.0

8 0.0 24 0.0 l 9 0.0 25 0.0 10 0.0 26 7.3' i

11 0.0 27 57.0 l 12 0.0 28 72.5 1

! 13 0.0 29 185.3 14 0.0 30 218.6 l 15 0.0 31 249.6 16 0.0 Generator on line but no net generation.

l l

h

TSP-3 .

Attachment TSP-3C issue 2 Page 1 of 1 Ut{lT_SHUIDOWNS AMD POWER R[ DUCTIONS DOCKET NO.10-267 UNIT NAME Fort St. Vrain Unit No. 1 DATE June 15. IM8 COMPLETED BY Frank Ju novaghek REPORT MON ill TELEPliONE 13031 620-1007 MAY. 1938 I i 1 1 I IMtIHOU 0T1 l l 1 1 I IsetuTTING I 1

l 1

l 1

l CAUSE Arid CORRECTIVE ACTION

-l I NO. I DAIL IIYPE DURAllON 1 REASON lDOWN I I LER # ISYSTEMICOMPONENil 10 PREVENT RECURRENCE i l l I l l lii[ACIOR I l C_00[ l COL 1 I I I I I I I I I I I 188-091 880'206 i r 1 484.0 ffr 1 A i I I i l l 3 1 88-009 i JA 1 Tl 1 Automatic Reactor Scram On fligh liot Reheat i 1 l 1 l l l Temperature Due To An Intermittent l i l i 1 1 l l l l [ Ma l f~unc t i on In Ibe Roheat Tempe ra ture l l l l 1 l l i

1 l l Averaging Ci rcui t. A Monitoring Program i l l I I 1 1 1 l l l Will Be E stabl ished To iden.iry the i I l t i I i i 1 1 I Matrunction.

I I I I I I I I I I i l i l I i I I i i l i i I i i 1 I I l I I i i i l I i l i i l I i I i i i i l l l l

l l l I I I i 1 I I I I I i I I I i I I I i I i I I i I i l I i l i l i I 1 1 I I l i I I i i i i l I I I I I I I i I I I 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 1 I I I I I I I I I

I I I I I l l l l I l l l l l l l l l t i l I I I I i 1 1 I I I I I I I I I I I I i I 1 1 I I I I I i 1 1 1 I i 1 1 I I I I I I' I I I I I I I I I I i I 1 1 I I I i 1 1 l_ l i I I I I I I I I I I I I I I I I I I I I I I 1 1 I l l I I I . I I I I I I I  ! I I I I -

i l I i I I I I I I I I I I I i 1 I I I I

1 I I I l I

REFUELING INFORMATION I -

1 I l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. I April 4, 1989 l 1 l l l 3. Scheduled date for restart l May 27, 1989 l l following refueling. l l I I l l 4. Will refueling or resumption off No l l operation thereafter require a l l l technical specification change l l l or other license amendment? l l l l l l If answer is yes, what, in  ! ---------------- l l general, will these be? l l l 1 I l If answer is no, has the reloadi 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 l to determine whether.any unre- l l l Viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? l (

l I l l If no such review has taken l 1988 l l place, when is it scheduled? l l l l l l 5. Scheduled cate(s) for submit- l l l ting proposed licensing action I ---------------

l l and supporting information. l l l 1 I l 6. Important licensing considera- l l l tions associated with refuel- l l l ing, e.g., new or different l l l fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant 'l l l changes in fuel design, new l l

, l operating procedures. l l l l l

+

l 7. The number of fuel assemblies ! I l (a) in the core and (b) in the ! a) 1482 HTGR fuel elements l l spent fuel storace pool. I b) 0 spent fuel elements l 1

- + - - _, ,-n - ,---,

i e i

REFUELING INFORHATION (CONTINUED)

L l i l l 8. The present licensed rpent.fuell [

l pool storage capacity and the l l l size of any increase in 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 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 1996 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-791001370 between .I l charged to the spent fuel pool l Public' Service Company of l

,' assuming the present licensed l Colorado, and General Atomic l l capacity. l Company, and 00E.* l 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 estimated that the eighth fuel segment will be discharged in 1996.

6

__- - __ - ____________ - __ - _______ -

Retrieved from "https://kanterella.com/w/index.php?title=ML20196C067&oldid=2987080"