ML20214A052

Monthly Operating Rept for Oct 1986

ML20214A052
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
P-86636, NUDOCS 8611190177
Download: ML20214A052 (8)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 153 "'

OCTOBER, 1986 tl

8611190177 861031 PDR

R ADOCK 05000267 8 I PDR i

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 October 1986.

1.0 NARRATIVE

SUMMARY

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

The reactor was in an intentional loss of forced cooling condition from October 14, 1986, to October 27, 1986, to allow Change Notice and corrective maintenance work on the condensate system and 150 pound steam header. During this period, forced circulation was recovered periodically to verify core temperatures.

On October 13, 1986, at 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br />, a reactor scram actuation of the Plant Protective System (PPS) occurred due to an indicated rate of change high on nuclear instrument channels 3 and 5. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 86-028, preliminary.

During the month of October, the General Accounting Office performed an audit of the Fort St. Vrain Radiological Emergency Response Plan with respect to the Chernobyl accident and potential implications to United States reactors.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATIDN 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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Atttchest= 3 Itsue 2 ottunsC dan Rrroc DOCKET so. 50-267 DA:s November 14, 1986 Conrtr:tD :T F. J. Novachek tr zymont .(303) 620-1007 errunsC $*.AT 5 nozzs

1. Dai same: Fort St. Vrain Unit No. 1

. Reporting Period: 861001 through 861031

3. Lice sed Thermal Power (Wt): 842 4 Nameplate Rating (Cross se): 342

5. Design Electrical Racing Olet **): 330

6. Maximum Dependable Cao city (Cross We): 342

7. Maximus Dependable Capacity (Met We): 330

8. If Changes occur in capacity Racings (Iteas Number 3 Through 7) Since Last Report, Cive Reasons:

None

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

10. Reasons for nestrictions, If Any: Per commitment to the Nuclear Renulatorv cnmmic=4nn.

remain shutdown eendine completion of Environmental Oualification mndifir einne _

This Month Year to Date Cumulative

n. hurs is amporting Period 745 7.296 64.321

12. sunber of sours Reseter was critical 0.0 2,456.6 30,537.8

13. Reactor lessrve Shutdova Ecurs 0.0 0.0 0.0

14. nours Generator on-Line 0.0 1.087.1 19.555.1

15. cnit Reserve Shutdown seurs 0.0 0.0 0.0

16. Cross Thermal Energy Generated (st) 0.0 370.316.6 10.265.190.R

17. Cross Electrical EnerEy Generated (WR) 0.0 85.402.0 1.111.QQ6.n

18. Net Electrical Energy Generated (WE) -1.587.0 55.416_0 7.491.7no n

19. Cait sorrice Tactor . O_0 1A Q gn A

20. cast Avanability Tactor _. __

0.0 14.9 10.4

11. Unit Capacity Tactor (Using HDC 3et) 0.0 2.3 11_o

22. Onit capacity Tactor (Using DEE Net) 0.0 2.3 11.o

23. Unit Forced outage Rate 100.0 R9_1 A1 %

l 24 Shutdowns Scheduled over Nort 6 &nths (Type, Date, and Duration of Each): Environmental Qualification modifications, 861101, 1464 hours0.0169 days <br />0.407 hours <br />0.00242 weeks <br />5.57052e-4 months <br />.

25. If Shut Down at Zad of Report Period. Estimated Date of Startup: December 31. 19R6

26. Units In Test Status (Frior to Cornnercial operation): Forecast Achieved l Ix:::AL CRInCAL::T N/A N/A 1

IsInAL ELECn:CII: N/A __

N/A Co.wrRC:AL OFIRA U CN N/A N/A

, AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date November 14, 1986 Completed By F. J. Novachek Telephone (303) 620-1007 Month OCTOBER 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 0.0 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

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REFUELING INFORMATION I I I 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. I March 1, 1988 l l l l l 3. Scheduled date for restart l June 1, 1988 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 1 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 l 1986 l l place, when is it scheduled? I 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 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 spent fuel storage pool. I b) O spent fuel elements l

.a REFUELING INFORMATION (CONTINUED) 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-SC07-79ID01370 between l l charged to the spent fuel pool l Public Service Company of l l assuming the present licenttd 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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16805 WCR 19 1/2, Platteville, Colorado 80651 November 14, 1986 Fort St. Vrain Unit No. 1 P-86636 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 OCTOBER, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of October, 1986.

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

Sincerely,

.h(Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm

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