ML20153B136

Monthly Operating Rept for Feb 1988

ML20153B136
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/29/1988
From:	Fuller C, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-88103, NUDOCS 8803210409
Download: ML20153B136 (9)

Text

~. . . _ _ ..

1. r; w

f e

FUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY O ERATIONS REPORT N0. 169 February, 1988 4

J l

l l l t 1

1 .

l i

=

880321040? 880229 M

PDR ADOCK 05000267 8/ l j, R DCD l

l

. - . - - - _ . . . - . , . . - . . . . . - - - . . - . - . , . . ~ . . - - . - - , _ . . . - . - - . . - . , , . . - - - . . - - _ - . . . . , . - - - _ _ - , -

4

.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. DPR-34. This report is for the month of February, 1988.

1.0 NARRATIVE

SUMMARY

nc -OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On February 3,1988, at 1857 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.065885e-4 months <br />, "D" helium circulator. tripped on programmed speed low due to a speed cable failure during testing. The turbine generator and reactor automatically ran back to 50% on the circulator trip, as designed. Reactor power was reduced to 30% and "D" helium circulator was returned to service at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />. The reactor remained at 30% power through February 6, 1988, while helium circulator speed cable problems were evaluated.

On February 10, 1988, at 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />, with the reector operating at 77% power, "A" helium circulator tripped on programmed speed l low because of a misconnected speed cable. The turbine generator 4

and reactor ran back to 50% on the circulator trip, as designed.

The main discharge valve on "B" boiler feed pump failed to close on the circulator trip, causing "A" and "C" boiler feed pumps to back off line and resulting in a drop in emergency feedwater header pressure to the backup bearing water system. When the feed pump output control system was placed in manual to recover emergency feedwater hea er pressure, a transient occurred in the bearing water system, resulting in trips of "B" and "D" helium circulators and an automatic shutdown of Loop I at 1608 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.11844e-4 months <br />.

With only one helium circulator remaining in operation, management ordered a manual reactor scram. This event was l investigated and reported to the Nuclear Regulatory Commission in l Licensee Event Report 88-002.

1 Also on February 10, 1988, at 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />, an Unusual Event was declarea when a reactor plant exhaust stack gas radiation monitor indicated an unplanned release of radioactivity. The reactor plant exhaust stack activity levels returned to normal at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />. The plant remained in an Unusual Event classification while ir.vestigating the elevated activity indications. The Unusual Event was terminated on February 11, 1988, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, when the source of the unplanned release and elevated activity in the gas waste system were identified. The source of the unplanned release was determined to be a faulty relief valve in the core support floor gas vent line. The total amount of activity released was conservatively estimated at 426 millicuries

, of noble gases. A one-hour notification was made to the Nuclear i Regulatory Commission at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> in accordance with l

e 10CFR50.72(a)(1)(1).

5

- _ _ - - . _ _ ...__ _ . - _~. _... _ ,_ _ .____. _ ._ _. ,.._.__.___ ___ __. _ _ _,.__ _... _ ,. .

On February 11, 1988, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, the. Plant Protective System

-reactor scram logic and alarm _ circuitry was actuated on Wide Range Channel neutron flux rate of change _high. The cause of the scram actuation was electrical noise induction in the wide range nuclear instrumentation channels. This event has been investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 88-003.

The reactor ~ was taken critical on February 13, 1988, at 0258 hours0.00299 days <br />0.0717 hours <br />4.265873e-4 weeks <br />9.8169e-5 months <br />. The turbine generator was returned to service on February 14, 1988, at 0728 hours0.00843 days <br />0.202 hours <br />0.0012 weeks <br />2.77004e-4 months <br />. . Reactor power was held to less than 30% while helium circulator speed cable connectors were repairec.

On February 24, 1989, at 2251 hours0.0261 days <br />0.625 hours <br />0.00372 weeks <br />8.565055e-4 months <br />, the turbine generator automatically tripped on indicated low main steam pressure. The cause of the trip was determined to be a' faulty valve position in a steam pressure instrument line. The turbine generator was returned to service on February 25, 1988, at 1214 hours0.0141 days <br />0.337 hours <br />0.00201 weeks <br />4.61927e-4 months <br />.

On February 26, 1988, reactor power was increased to approximately 78%, following the completion of speed cable connector repairs.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 7

OPERATING DATA REPORT DOCKET NO. 50-?67 OATE March 15. 1988 COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 OPERATING STATUS h0TES

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

2. Reporting Period: 880202 throuah 880229

3. Licensed Thermal Power (Wt): 842 4 hameplate 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 In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted, If Any (Net MWe): 770.6

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

This Month Year To Date Cumulative

11. Hours In Reporting Period 696 1.440 75.985

12. Number Of Hours Reactor Was Critical 661.1 1.405.1 34.851.8 r

13. Reactor Reserve Shutdown Hours 0.0

{

0.0 0.0 14 Hours Generator On-Line 619.2 1.363.2 22.948.7 l 15. Unit Reserve Shutdown Hours 0.0 0.0 0 f) ,,,,,,

i

16. Gross Thermal Ene.gy Generated (MWH) 240.383.5 643.246.3 11.576.580.9

17. Gross Electrical Energy Generated (MWH) 80.603.0 232.034.0 3.774.254.0

18. Net Electrical Energy Generated (MWH) 74.632.0 91R.094.0 3.334.121.0

{ 19. Unit Service Factor 89.0 94.7 30.2

20. Unit Availablilty Factor 89.0 94.7 30.2 l 21. Unit Capacity Factor (Using MDC Net) 32.5 45.9 13.3

22. Unit Capacity Factor (Using DER Net) 32.5 45.9 13.3

23. Unit Forced Outage Rate 11.0 5.3 63.3 j 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Helium Circulator Reoairs. 880502. 2.304.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

25. If Shut Down At End Jf Report Period Estimated Date Of Startuo: N/A.

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

l l

-- AVERAGE DAILY UNIT POWER LEVEL-

. '.c' - ' Docket No '50-267 Unit Fort St. Vrain Unit No. 1 Date March 15, 1988 Completed By F. J. Novachek

~ Telephone (303) 620-1007 Month FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 226.1 17 69.3 2 226.3 18 71.5 3 204.8 19 67.5 4 68.1 20 67.2

-5 75.9 21 64.2 6 73.8 22 69.9 7 98.6 23 _ 68.9 8 130.1 24 81.3 9 172.4 25 19.8 10 138.1 26 177.8 11 0.0 27 232.8 12 0.0 28 230.8 13 42.5 29 232.0 i

14 69.8 30 N/A 15 72.4 31 N/A 1

16 71.1

• Generator on line but no net generation.

_ _ _ _ _ _ _ _ _ _ -__-__ _ _ _ _ _ _ _ _ _..____ . . . _ _ _ m ._ __ .m._ ,

4  %

6 9

ISP-3 '

Attachment TSP-3C Issue 2 Page 1 of 1 UNIT CHUTDOWNS AND FOWER 74 SUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vrain Unit Noy DATE Ma rch 15. 1988 COMPLETED BY Frank J. Novachek TELEPHONE (303) 620-1007 REPORT MONTH FEBRUARY. 1988 I l l l  ! lMLIHOD Of1 I l l l l l l l l lSHUITING l l l l CAUSE AND CORRECTIVE ACTION l ,

1 NO. I DATE ITYPLI DURATION l REASON lDOWN l LER g ISYSTEMICOMPONENil TO PREVENT RECURR[NCE l l l l l l lRJACTOR I l CODE ICODE I l l l l l l l l l_ l l 'l 168-031 880203 l I I N/A l A I 4 l N/A I JA l SIC l D Helium Ci rcula tor T rip And Powes r I i i i l i l l l l l Reduction Due To Speed Cable Problems. I I I I I I I l I i .

I 188-041 880210 i f l 63.4 Hr l H I 2 1 88-002 1 JA ,

SIC l Manual Reactor Scram Following 3 Helium l I I I  ! l l l l [ l Circulator Trips Due To Misconnected Speed -

1 I I l l l l l 1: 1 Cable. Positive Control Of Speed Cable 1 I I l l l l l  ! Installation Instituted.

I I I I I I I I I I L 188-051 880224 i F i 13.4 Hr l A l 4 i N/A l SB -1 Pts I turbine Trip On False Low Main Steam Il l i I i 1 l l l l Pressure Indication Due To Faulty Valve. I ,

I l l l l l l l Repaired V-5297. I I l l l ll l l .I I I l l l l ll l' I I Il I 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 i 1 1 1 1 1 1 I I I l l .I i 1: I i l l I I I I I I I I I I I c  ! I I .

I I I I I I I; I I I I I <

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

I .l 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 'l' I I i l l I I I I I I I I I I I I I I I I I l l 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 1 I I i

REFUELING INFORMATION l l ~

l l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l l- l l 2. Scheduled date for next l l l refueling shutdown. l April 4, 1989 l l . l l l 3. Scheduled ~date for restart l May 27, 1989 l l following refueling. l l 1 -

l 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? I l l I I l If answer is yes, what, in l ---------------- l l general, will these be? I l l l l l If answer is no, has the reloadl 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 1 to determine whether any unre- l l

I viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section l [

] 50.59)? I l i

I l l l If no such review has taken l 1988 l l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action l ------------- -- l l and supporting information. l l l l l 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 l viewed design or performance l l t

l analysis methods, significant l l l changes in fuel design, new l l l coerating procedures. 1 l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) O spent fuel elements l i

l l

i i

[

o I' .

s REFUELING INFORMATION (CONTINUED) l- 1 I l 8. The present licensed spent fuell l

-l pool storage capacity and the l l size of any increase in - 1 Capaci?y is limited in size to l l l licensed storage capacity that l.about-c.ie-third of core l l has been requested or is I (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l

-l assemblies. l l l 1 l l 9. The projected date of the last i 1996 under Agreements AT(04-3)-633]

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 I l assuming the-present licensed l Colorado, and General Atomic l l capacity. I Comoe ny, 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 accommodtte eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1996.

1 a

I w , --, y,, we ,m . nw, , ,----- - v. n , - - - . - , - --,-nn-,,-n-- , - - --- . - , . - -- - - . . - -, - - - - - - - - - - - - - - - - - - ~ . -

h Public Service ~ ar#!L..

16805 WCR 19 1/2, Platteville, Colorado 80651 March 15, 1988 Fort St. Vrain Unit No. 1 P-88103 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

FEBRUARY, 1988 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Opera.ing License No. OPR-34

Dear Sirs:

Enclosed, please find the Monthly Operations Report for the month of February, 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,

$bu C. H. Fuller Manager, Nuclear Production Enclosure l

cc: Regional Administrator, Region IV i ATTN: Mr. T. F. Westerman, Chief I

Projects, Section B l

Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain CHF:djm l

l Ah

'p