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Monthly Operating Rept 167 for Dec 1987
	ML20147D906
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1987
From:	Novachek F, Robert Williams; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	P-88028, NUDOCS 8801200363
	Download: ML20147D906 (9)
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h PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION

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MONTHLY OPERATIONS REPORT NO. 167 December, 1987 t 1

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My 8801200363 871231 :

PDR ADOCK 05000267 R DCD

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated undar the provisions of the Nuclear Regulatary Commission Operating License No. OPR-34. This report is for the month December, 1987, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On December 7,1987, while performing a post maintenance test on firewater deluge control relay CR-4505, an error in the test procedure resulted in a trip of the Reserve Auxiliary Transformer and a Loss of Outside Electric Power (LOEP) at 1745 hours0.0202 days 0.485 hours 0.00289 weeks 6.639725e-4 months . The emergency diesel generators automatically started and loaded, and all needed equipment functioned as designed. Outside electric power was restored at 1847 hours0.0214 days 0.513 hours 0.00305 weeks 7.027835e-4 months . This event was investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-028.

Also on December 7, 1987, at 2248 hours0.026 days 0.624 hours 0.00372 weeks 8.55364e-4 months , a reactor scram actuation was received on neutron flux rate of cnange high on all three wide range chanrals. A second reactor scram actuation was received on December 8, 1987, at 1320 hours0.0153 days 0.367 hours 0.00218 weeks 5.0226e-4 months . Subsequent investigation determined the cause of the scram actuations to be electrical noise induced into the wide range channels as a result of the mislocation of terminal TB8-53 on cable 7487 following cable repa rs. This event was investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-029.

The reactor was taken critical on December 11, 1987, at 0925 hours0.0107 days 0.257 hours 0.00153 weeks 3.519625e-4 months , following the completion of fire damage repairs.

On December 13, 1987 Technical Specification Surveillance Procedure ESR 8.1.1.a-M ("Radioactive Gaseous Effluent Vent Monitor System Source and Functional Test") exceeded the monthly interval, including the 25% allowable extension. This condition was discovered on December 14, 1987, at which time the surveillance was successfully completed. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-030.

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l Or, December 15, 1987, at 1948 hours0.0225 days 0.541 hours 0.00322 weeks 7.41214e-4 months , the turbine generator was placed on line. At 2338 hours0.0271 days 0.649 hours 0.00387 weeks 8.89609e-4 months , D helium circulator tripped on buffer-mid-buffer, resulting in a minor moisture ingress into the primary coolant system. At 2339 hours0.0271 days 0.65 hours 0.00387 weeks 8.899895e-4 months , the reactor dew point exceeded Technical Specification LC0 4.2.11 limits for the existing average core outlet temperature and a 24-hour grace period was entered.

The reactor operator started reducing reactor power to return to compliance with LCO 4.2.11. The turbine generator was manually tripped at 2344 hours0.0271 days 0.651 hours 0.00388 weeks 8.91892e-4 months . The reactor was returned to compliance with LCO 4.2.11 on December 16, 1987, at approximately 0220 hours. The turbine generator was returned to service on December 19, 1987, at 2035 hours0.0236 days 0.565 hours 0.00336 weeks 7.743175e-4 months .

On December 24, 1987, at 1306 hours0.0151 days 0.363 hours 0.00216 weeks 4.96933e-4 months , following a trip of "C" helium circulator, the turbine generator tripped offline on low main steam temperattre. The turbine generator was returned to service at 1335 hours0.0155 days 0.371 hours 0.00221 weeks 5.079675e-4 months .

On December 25, 1987, at 1328 hours0.0154 days 0.369 hours 0.0022 weeks 5.05304e-4 months , the reactor was automatically scrammed by the Plant Protective System on high hot reheat steam temperature while operators were adjusting primary coolant flow. The reactor was taken critical at 1244 hours0.0144 days 0.346 hours 0.00206 weeks 4.73342e-4 months on '

December 27, 1987. The turbine generator was returned to service at 1742 hours0.0202 days 0.484 hours 0.00288 weeks 6.62831e-4 months on December 28, 1987. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-031, 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, t

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OPERATING DATA REPORT LCCKET NO. 50-267 DATF January 15. 1988 i

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COMPLETED BY F. J. Novachek TELEPHONE (3Q3) 620-1007 OPERATING' STATUS h0TES ,

1. Unit Name: Fnet St. Vrain. tini t Nn. 1

2. Reporting Period: 871201 throuah 871231

3. Licensed Thermal Power (MWt): 842

4. Name) late Rating (Gross MWe): 342

3. Design Electrical Rating (Net MWe): 110 3

6. Maximum Dependable Capacity (Gross MWe): 347

7. Maximum Dependable Capacity (Net We): 330 ;

8. If Changes Occur In Capacity Ratings (!tems 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: _Seanalysis of safe shutdown cooling following a 90 minute interruotion of forced coolina.

This Month Year To Date Cumulative +

i-- - 11. Hours In Reporting Period 744 8.760 74.545 -

12. Number Of Hours Reactor Was Critical 447.4 2.908.9 33.446.7

13. Reactor Reserve Shutdown Hours 0.0 0.0

0.0 .

14 Hours Generator on-Line 218.*/_

2.030.4 21. 588i.Ji_.

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 87.441.7 667.934.8 10.933.334.6 !

17. Gross Electrical Energy Generated (MWH) 18.435.0 208.224.0 3.542.220.0

18. Net Electrical Energy Generated (MWH) 14.649.0 167.747.0 4 3.116.077.0 I

19. Unit Service Factor 29.4 23.2 29.0

20. Unit Availablilty Factor 29.4 21, Unit Capacity Factor (Using M.nC Net)

23. L 29.0 f 6.0 5.8 12.7

22. Unit Capacity Factor (Using DER Net) 6.0 5.8 '

12 . 7 _.,

j 23. Unit Forced Outage Rate 70.6 76.8 64.6 i ;

24 Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Helium Circulator ,

Renairs. 880312. 2.303.0 hours0 days 0 hours 0 weeks 0 months

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

26. Units In Test status (Prior To Comercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A

INITIAL ELECTRICITY N/A N/A h COMMERCIAL OPERATION _

N/A N/A J

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AVERAGE DAILY UNIT POW d LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date January 15, 1988 Completed By F. J. Novachek Telephone (303) 620-1007 Month OECEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) '

1 0.0 17 0.0 t 2 0.0 18 0.0 i 3- 0.0 19 0 '. 0

4 4 0.0 20 52.8 .

5- 0.0 21 68.8

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6 0.0 22 98.4 7- 0.0 23 125.7 8 0.0 24 99.0 .

'9 0.0 25 35.3 10 0.0 26 0.0 11 0.0 27 0.0 i i

12 0.0 28 10.3 13 0.0 29 67.5 '

I 14 0.0 30 67.8

! 15 0.6 31 67.3 16 0.0 h Generator on line but .1o net generation, i !

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TSP-3 Attachment TSP-3C lssue 2 Page 1 of 1 UNIT SHUTDOWNS AND POWER REDUCTION}

DOCKET NO. 50-267 UNIT NAME fort St. Vra in Unit No. 1 DATE enua ry 15. 1988 COMPLETED BY f rank J. Novachek REPORT MONTH DECEMBER. 1987 l l l l l lMLTHOD Ull I I l l l l 1 l 1 ISHUTTING 1 l l l CAUSE AND CORRECTIVE ACTION

I NO.'l DATI ITYPEI DURATION I REASON IDOWN 1 LER g ISYSTEMICOMPONENil TO PREVENT ftECURRE NCE I l I 1 l l l REACTOR I IC_OJ L lCODE I I I i l l I l l t l I 18 7- t:41 871201 l r i 355.8 hr l A l 2 I 87-023 i l l i SB l RV i REPAIR HYDRAULIC OIL FIRE DAMACE. l l l l l l l l l 1 1 I I I (CONilNUED FROM 871003) l I I I I I I I 92.8 hr i H 4 i N/A i

l181- 151l 8 71 ? t *>; lI l l AB 1 CMP 1 MOISIURE INGRESS FOLLOWING TRIP Of D I l l l l l l l HEllUM CIRCULATOR.

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l l l l l 187-161 8712284 I i 1 0. *> h r l H I 4 l N/A I AB 1 CMP 1 IURBINE TRIP ON LOW MAIN STEAM IEMPERATURE l l l l l l l l l l I I I I I l FOLLOWING TRIP OF C HELIUM CIRCULATOR. 1 I I l t i i 181-171 8712?$ 1 I l 76.7 hr I G ll 3 1 87-031 l ZZ l ZZZZZZ l REACTOR SCRAM ON HOT REHEAT T[MPERATURE l l l l l l 11 l l l 1 HICH DUE TO OPERATOR ERROR.

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

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

REFUELING INFORMATION I I l l 1. Name of Facility l Fort St. Vrain bnit No. 1 _, l l l 1 l 2. Scheduled date for next l l l refueling shutdown. 1 April 3, 1989 l 1 l l l 3. Scheduled date for restart l May 26, 1989 l l foll,owing refueling. l l l l l l 4. Will refueling or resumption ofl 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 l general, will these be? I l l l l l If answer is no, has the reload l 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)? I l l l l l If no such review has taken i 1988 l l place, when is it scheduled? I l l l l l 5. Scheduled date(s) for submit- l l l ting r coposed licensing action l ---------------- l l and *. pr,orting information. l l l 1 l l 6. Important licensing considera- l l l tions associated with refuel- l l l ing, e.g., new or different l l

[ f"el 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 1 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 scent fuel storage pool. I b) 0 spent fuel elements l

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i REFUELING INFORMATION (CONTINUED)

I 1 l l 8. The present licensed spent fuell l 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 l about one-third of core l l has been requested or is I (approximately 500 HTGR elements).1 l planned, in number of ftel l No change is planned. I l assemblies. l ,

l 1 I i l 9. The projected date of the last l 1996 under Agreements AT(04-3)-6331 l refueling thst can be dis- l and DE-SC07-79ID01370 between l l charged to the spent fuel pool l Public Service Company of l t l assuming the present licensed l Colorado, and General Atomic 1 l capacity. I Company, and 00E." l 2

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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. !

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O eudiic service ~ =<=..-

16805 WCR 19 1/2, Platteville, Colorado 80651 January 15, 1988 Fort St. Vrain Unit No. 1 P-88028 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

DECEMBER, 1987 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License No. DPR-34 0

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of December, 1987, 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.

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Sincerely, t

R. O. Williams, Jr.

Vice President, Nuclear Operations Enclosure cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief l Project Section B j Mr. Robert Farrell l

Senior Resident Inspector l Fort St. Vrain RDW:djm l)

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ML20147D906

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