ML20211H951

Monthly Operating Rept for Jan 1987

ML20211H951
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/31/1987
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-87066, NUDOCS 8702260338
Download: ML20211H951 (8)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 156 January, 1987 I=

B702260338 870131

, PDR ADOCK 05000267

R PDR

- s 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 January 1987.

1.0 NARRATIVE

SUMMARY

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

Prefabrication work and snubber modifications were initiated for the Evaporator / Economizer /Superheater (EES) vent line modification (CN-2397 and CN-2412).

Potentially defective Westinghouse AR 440 relays are in the process of being replaced (CN-2191 and CN-2514A).

On January 29, 1987, during a review of the results of surveillance SR 5.2.1.bl-2.5Y, it was determined that the failure of tnree penetration safety valves to meet their Technical Specification Limiting Safety System Setting (LSSS) acceptance criterin was reportable. This will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-001, 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 e

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• Tsr-3 Attschment-33

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e treue 2 Pep l e'f 3 orrume DATA tr?oc Doccrr ss. 50-267 DaTE February 12. 1987 CotTLETED IT F. .I. Novnchek TrLzruont (303) 620-1007 orru m e s!A C S '

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

. Reportins Period: 870101 through 870131

3. Licensed thermal Power (w s): 842

4. Nameplace Rating (Gross W e): 342

3. Design Electrical Rating (Net We): 330

6. Maximum Dependable Cacacity (Gross Ee): 342

7. Maximua Dependable Capacity (Net We): 330

8. If Changes occur in Capacity Ratings (Items Number 3 "hrough 7) Since Last Report, Cive Reasons:

None

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

10. Reasons for Restrictions, If Any: Per commitment to the Nuclear Reculatory Comi s s ion .

remain shutdown nendinc completion of Environmental Quali fication modifications.

This Month Yaar to Date Cumulative

11. Hours in Reporting Feriod 744 744 66.999

12. Nu=ber of Bours Reactor Vas critical 0.0 0.0 30.537.8

13. Raaetor Reserve shutdown Ecurs 0.0 0.0 0.0

14. Rours cenerator on-Line 0.0 0.0 19.555.1

13. Unit Reserve shutdown sours 0.0 0.0 0.0

16. cross Thermal raergy cen rated os.s) 0.0 0.0 10,265,399.8

17. cross tiectrical Energy cenerated (wa) 0.0 0.0 3,333.996.0

18. Yet Electrical Energy cenerated us.'u) -2,184.0 -2,184.0 2,946.096.0

19. Unit Service Tactor .

0.0 0.0 29.4

20. Unit Availability Tactor 0.0 0.0 29.4

21. Unit Capacity Tactor (Uning NDc Net) 0.0 0.0 13.4

22. Unit Capacity Tactor (Using DER Net) 0.0 0.0 13.4

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23. Unit Forced outage Rate 100.0 100.0 63.1

24. $hutdowns Scheduled over Next 6 Nnths (Type, Date, and Duration of Each): Environmental Ouali f f eation modifications, 870201, 1064.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

• 5. If Shut Down at Ind of Report Period, tatir.ated Late of Startup March 17, 1987

26. Unita In Test Status (Frior to Co*:sercial operation): Torecast Achieved tx:nAL cunen:n N/A N/A _

INinn rtte ncIIT N/A N/A cc.esRc:a er:uncN N/A N/A

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date February 17, 1987 Completed By F. J. Novachek Telephone (303) 620-1007-Month January

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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 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' O.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

• Generator on line but no net generation.

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2 TSP-3 Attachment TSP-3C lasue 2 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra in Uni t No. 1 DATE Februa ry 12. 1987 COMPLETED BY Frank J. Novechek TELEPHONE (303) 620-1007 REPORT MONTH JANUARY. 1986 l l l l l l METHOD OFI l l.

l l l l l SHUTTING l I CAUSE AND CORRECTIVE ACTION I NO. I DATE ITYPEl DURATION REASON DOWN l* LER g . SYSTEM COMPONENT TO PREVENT RECURRENCE I I I l REACTOR l CODE l CODE I .

I I l I 186-03: 861201 1F i 744 hr D 1 l N/A ZZ ZZZZZZ Envi ronmenta l Qua l i fica tion i l i I .

modifications

! I I I I I I I I i i i l I I i l i i 1: I I g 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 I I I I I I I I I I I i 1 I l 1 I I I 1 I I ll 1 1 I I I I I -

l l 1 I I I I I I I I I I I I I I I i 1 i L l i I I I I I I l l I I I ll ,

I i 1 I I I I

I I I I '

I i i i i i -l-1 I I I I I I I I i 1 1 1 1 l 1 1 - 1 I I I 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 September 1, 1988 l l l l l 3. Scheduled date for restart l November 1, 1988 l l following refueling. l l l l 1 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 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 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 l l l 5. Scheduled date(s) for submit- l l l ti ng proposed licensi ng 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 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 1 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. l b) 0 spent fuel elements l

REFUELING INFORMATION (CONTINUED) l l l 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 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 1992 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-791001370 brtween 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.* l

• 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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h Public Service ~ act".L 16805 WCR 19 1/2, Platteville, Colorado 80651 February 17, 1987 Fort St. Vrain Unit No. 1 P-87066 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 JANUARY, 1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

January, 1987.

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

Sincerely, J!h,$2 f J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm gh ob

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