ML20212P948

Monthly Operating Rept for Feb 1987

ML20212P948
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-87102, NUDOCS 8703160399
Download: ML20212P948 (9)

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

l MONTHLY OPERATIONS' REPORT NO 157 February, 1987 l

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' 8703160399 DR 870228 -

ADOCK 05000267 PDR

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' 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 -

DPR-34. This report is for the month of February 1987.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown during the entire month of February for Environmental Qualification modifications.

On February 2, 1987, an Engineering evaluation of the Emergency Diesel Generator (EDG) control circuitry determined that given predetermined unique conditions a single point exists where the redundant system independence is compromised, such that a single component failure could cause loss of both diesel generator sets.

This single failure could allow both diesel generators to be paralleled together without synchronizing. Administrative controls have been established to maintain one of the 480 VAC bus tie breakers in the racked out position until permanent modifications can be . implemented. This event has- been investigated and reported to the Nuclear Regulatory Commission in

.- Licensee Event Report 87-002.

q On February 3,-1987, while performing Functional Test FT-2191-5, simultaneous load shedding on 480 VAC Bus 2 and Bus 3 was inadvertently initiated-causing 1B Emergency Diesel-Generator-to-automatically start, and a Plant Protective System (PPS) automatic reactor scram actuation on undervoltage. This event has been investigated and reported to the.. Nuclear Regulatory Commission in Licensee Event Report 87-003.

On February 15, 1987, it was determined that an unanalyzed liquid waste release had occurred on Februery 7, 1987. This event is being investigated and will be reported to the Nuclear Regulatory Commission in Licensee Event Report 87-004.

On February 19, 1987, during work on "D" Helium Circulator drain malfunction alarm, a Plant Protective System (PPS) Loop II shutdown actuation occurred. This Event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-004.

On February 23, 1987, the Manager of Nuclear Production, Mr. J.

W. Gahm, resigned. The Vice President of Nuclear Operations, Mr.

R. O. Williams, has assumed the duties of the Manager of Nuclear

. Production until a replacement is named.

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On February 26, 1987, Public Service Company of Colorado gave a

presentation to the Nuclear Regulatory Commission requesting

permission for restart. Their decision is pending.

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

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Attechrent-33 o* * .

Is;ue 2 P:se 1 er 1 orEnATInc DATA REPORT DOC 3ET T.J. 50-267 DATE March 10. 1987

• COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 OPERATING STATUS notes

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

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2. Raporting Feriod: 870201 throunh 870228

3. Licensed Thermal Power (wt): 842

4. Nameplate Rating (Gross we): 342

5. Design Electrical Rating (Net m e): 330

6. . Maximum Dependable Capacity (Gross we): 342

7. Mar 1=um Dependable Capacity (Net we): 330

8. If Changes occur in capacity Ratings (Items Number 3 Through 7) Since last Report, Cive Reasons:

None

9. Power Level To Which Restricted, If Any (Net HWe): 0.0

10. Reasons for Restrictions, If Any: Per commitment to the Nuclear Regulatory Commission, remain shutdown pending completion of Environmental Qualification modifications.

This Month Taar to Date Cumulative

11. Bours in Reporting Period 672 1.416 67.201

12. Nunber of Hours Reactor Was Critical O0 0.0 30.537.8

13. Reactor Reserve Shutdown Ecurs O_O O_O O_0

14. nours cenerator on-Lin. 0.0 0.0 19.555.1 _.

15. Unit Reserve Shutdown Bours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (ms) 0.0 0.0 10.265.399.8

17. Gross Electrical Energy Generated (HWB) 0.0 0.0 3.333.996.0 _.

18. Net Electrical Energy Generated (wH) -2.370.0 -4.554.0 2.943.726.0

19. Unit Service Factor 0.0 0.0 29.1

20. Unit Availability Tactor 0.0 0.0 29.1

21. Unit capacity Factor (Using MDc Net) 0.0 0.0 13.3 J

22. Unite.apacityfactor(UsingDERNet) 0.0 0.0 13.3

23. Unit Forced Outage Rate 100.0 100.0 63.6

24. Shutdowns Scheduled Over Next 6 lbaths (Type. Date, and Duration of Each): Environmental Ounli f f ention modifientions . 870301. 392.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

25. If Shut Down at End of Report Period. Estinated Date of Startup March 17_ 1987

26. Units In Test Status (Prior to Cot =nercial Operation): Forecast Achieved INITIAL CFJTICALITI N/A N/A

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INITIAL ELEc rJCIIT N/A N/A COMw.ERCIAL OPERATICN N/A N/A

.. , AVERAGE DAILY UNIT POWER LEVEL-Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date March 10, 1987 Completed By F. J. Novachek Telephone (303) 620-1007 Month February

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.0 17 0.0 2 0.0- 18 0.0 3 0.0 19 0.0 1

4 0.0 20 0.0 5 0.0 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 N/A 14 0.0 30 N/A 15 0.0 31 N/A 16 0.0 l

• Generator on line but no net generation.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra in Unit No. 1 DATE Ma rch 10. 1987 COMPLETED BY Frank J. Novechek TELEPHONE f3031 620-1007 REPORT MONTH MARCH. 1987 I METHOD OF I l l l 1

l SHUTTINC I CAUSE AND CORRECTIVE ACTION I I l l SYSTEM COMPONENT TO PREVENT RECURRENCE l NO. I DATE ITYPEl DURATION l REASON DOWN LER #

i REACTOR COD ( CODE I I i 1 l

l I I I I I D N/A l ZZ Z77777 Envi ronmenta l Que l l rica tion i 186-031 870201 i F I 672 hr iI l I

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4 REFUELING INFORMATION l l l l 1. Name of Facility l Fort St. Vrain Unit No.1 l l l l

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l 2. Scheduled date for next l l ._

l refueling shutdown. I November 1, 1988 l l l l l 3. Scheduled date for restart l January 1, 1989 l l following 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? l l l- 1 I 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)? l l l l l l If no such review has taken l 1987 l l place, when is it scheduled? l l

. l . I I l 5. Scheduled date(s) for submit- l l l ting proposed licensing action l ---------------- l l and supporting information. l l I I 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 f uel de sign or suppl i er, 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 1 I I 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

REFUELING INFORMATION (CONTINUED) l I . I

_ . _ _ _ , , , 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 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 i 1992 under Agreements AT(04-3)-633l 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 l l assuming the present licensed l Colorado, and General Atomic l l capacity. I Company, and DOE.* 1

• The 1992 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 1992.

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16805 WCR 19 1/2, Platteville, Colorado 80651 March 12, 1987 Fort St. Vrain Unit No. 1 P-87102 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267 ,

SUBJECT:

MONTHLY OPERATIONS REPORT FOR FEBRUARY, 1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

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

Sincerely, W

R. O. Williams, Jr.

Vice President, Nuclear Operations Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV R0W:djm lfI 3 sa+

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