ML20207P444

Monthly Operating Rept for Dec 1986

ML20207P444
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-87016, NUDOCS 8701160139
Download: ML20207P444 (8)

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PUBLIC SERVICE COMPANY OF CdLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 155

- December, 1986

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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 December 1986. ,

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

On December 9, 1986, at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br />,,a Reactor Building High Temperature Scram actuation was received on scram channels A and B. The cause of the scram circuit actuation was determined to be the use of a handheld radio in the control room. This event has been investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 86-029.

On December 17, 1986, during a review of DCAR-619, Nuclear Engineering Division determined that the emergency diesel generator low exhaust temperature switches and clutch position switches were not documented as being seismically qualified as

- required by their safety-related classification. This will be

_) investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 86-030.

During the month -of December the 4160V ITE breaker overhaul program was completed. This was a five year program.

Technical Specification discharge tests were successfully performed on Station Batteries "1B" and "1C".

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On December 31, 1986, a test was performed to install spool pieces between the fire protection system and the emergency feedwater header. This was done to verify that firewater cooldown of the reactor could be initiated within the time allowed by the FSAR analysis for safe shutdown cooling following a Design Basis Earthquake. The results of this test are being evaluated at this time.

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 i

,';  :: None f 4.0 MONTHLY OPERATING DATA REPORT A+ + wy

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OrrRATING STAT'JS nortS

1. Unit m.me: Fort St. Vrain. Unit No. I _.

2. Reporting Period: 861201 through 861231

3. Licensed thermal Power (Wt): R42

4. Nameplate Rating (Gross We): 342 S. Desisa Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Cross We): 342

7. Maximus Dependable Capacity (Net We): 330

8. If Changes Occur in Capeity Ratings (Items Number 3 Through 7) Since last Report. Give Raasons:

None

9. Power Lesel To Which Restricted. 1 .y (Net W e): 0.0

10. Reasons for Restrictiers, re wy Per_coninitment to the Nuclear Requlatory Commission, renain shutdown Dendic completion of Environmental Oualification modifications. ,

This Month Year to Date Cuimlative-

11. Hours in Reparting Period 744 8.760 65.785

12. Nunter of B:urs Reactor Was Critical 0.0 2.456.6 30.537.9

13. Reactor Reserve shutdown nours 0.0 0.0 0.0

16. nours ceneistor On-t.ine 0.0 1.087.1 19.555.1 15 cast Reserve Shutdown sours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (WH) 0.0 370.316.6 10.265.399.8

17. cross timetriest toergy cenerated (Mwii) 0.0 85.402.0 3.333.996.0 1a. Not Electrical Energy cenerated (wn) -1.841.0 52.007.0 2.948.280.0

19. Unit Service Tactor 0.0 12.4 29.7

20. Unit Availability Tactor 0.0 12.4 29.7

21. Unit capacity Tactor (Using HDC Net) 0.0 1.8 13.6

22. Unit capacity Tactor (Using DER Net) 0.0 1.8 13.6

23. Unit Forced Outage Rate 100.0 R7.6 69.6

26. Shutdowns Scheduled Over Next 6 tbntha (Type. Date, and Duration of Each): Environmental Qualification modifications. 870101. 1080.0 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 February 15. 1987 e

26. Units In Test Status (Prior to Comercial Operation): Torecast Achieved txtttAL CRITICAL 1rr N/A N/A .

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txtTIAL titCatcIIT N/A N/A cmecrRetAL ornAT1cx N/A N/A

. . AVERAGE DAILY UNIT POWER LEVEL.s. . . .

Docket No. 50-267 -

Unit Fort St. Vrain Unit No. 1,,in w- . .,s . i Date January 12'0c.1987 inw v rid /

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Completed By F. J. Novachek - .

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. - - ,..-:-- Month DECEMBER,'.1986 *' " ((. '_= ,,

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

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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

• Generator on line but no net generation.

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4 Attachment TSP-3C Issue 2 Page 1 of 1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-267 UNIT NAME Fort St; Vra in Unit No. 1 DATE Janua ry 12. 1987 COMPLETED BY Frank J. Novachek

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l l l l HETHOD OFI l l l 1 SHUTTING l CAUSE AND CORRECTIVE ACTION <a o tj t 1l i NO. I DATE ITYPEI DURATION I REASON DOWN I LER # SYSTEM COMPONENT TO PREVENT RECURRENCE ,

I I l l l REACTOR I :C00C CODE 'c /

I I I I l l I,86-031 861201 iF i 744 hr i D . 1 I N/A ZZ ZZZZZZ l Environmental Quallrication Cho -

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i REFUELING INFORMATION r Jre m rrs l ~

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l 1. Name of F&cility- .I Fort St. Vrain Unit No. 1 - +

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l l l l 2. Scheduled date for next l_ .

l l refueling shutdown. I 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 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? I l l 1 l l If answer is yes, what, in l ---------------- l l general, will these be? 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 ll 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 If no such review has taken 1; 1987 l place, when is it scheduled? I' l

11 l l l 5. Scheduled date(s) for submit- ll l l ting proposed licensing action l ----------------

l and supportine information. l 1;

l l l 6. Important licensing considera- l ll 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. I l l l l l 7. The number of fuel assemblics 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) 0 spent fuel elements l l.

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REFUELING INFORMATION (CONTINUED)

I 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 l licensed storage capacity that l about one-third of core l l has been requested or is l(approximately500.HTGRelements).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 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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16805 WCR 19 1/2, Platteville, Colorado 80651 January 12, 1987 Fort St. Vrain Unit No. 1 P-87016 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 DECEMBER, 1986

REFERENCE:

Facility Operating License No. OPR-34

Dear Sir:

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

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

Sincerely, J,,Y '

. W. Gahm Manager, Nucleat- Production Fort St. Vrain Nuclear Generatirg Station Enclosure cc: Mr. R. D. '4artin, Regional Administrator, Region IV JWG:djm gf IlI

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