ML20100A299

Monthly Operating Rept for Feb 1985

ML20100A299
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85078, NUDOCS 8503250433
Download: ML20100A299 (8)

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PUBLIC SERVICE COMPANY OF COLORADO

, FORT ST. VRAIN NUCLEAR GENERATING STATION t

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MONTHLY OPERATIONS REPORT NO. 133 February, 1985

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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, 1985.

-1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown during the entire month of February while investigation, refurbishment, and testing of the control rod drives continued.

"1A" helium circulator is being refurbished and analyzed in San Otego. A draft report, " Evaluation of Fort St. Vrain Metallic Components Exposed to Primary Coolant Chloride Contamination" is being reviewed and finalized for submit'tal to the Nuclear Regulatory Commission in March.

Extensive preparations to _ ready the fuel' deck for control rod drive and orifice assembly (CRDOA) refurbishment and cable replacement have been completed. Design of the refurbishment equipment necessary for working on up to five assemblies simultaneously is complete, and functional. Contract personnel arrived, went through necessary training, and began work on the first control rod drive and orifice assembly on February 6,1985. Work is proceeding much slower than expected due to procedural problems and parts availability. One control rod drive orifice and assembly has been fully refurbished and placed back in the core. The " assembly line" phase of refurbishment began on February 22, 1985, and four control rod N drive orifice assemblies are presently in various stages of ss refurbishment.

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 3

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.. .. 31'-3 At t achn:n t-3s tssue 2 doc m No. 50-267 cirur:sc cAn anour Dm March 11,1985 ccxrt.tTtD iT Frank Novachek m tracNE (303) 785-2224 or oaTINc s m us NoI!3

1. catt Na.e: Fort St. Vrain ,

7. Reporting Period 850201 through 850228

3. f.icensed Ibermal Power Oste): 842

4. Nameplate Racing (cross We): 342

5. Design Electrical Racing C;et We): 330

6. Maximus Dependable Capacity (cross We): 342

7. Maximum Dependable Capacity (Net We): 330

8. If Changes Occur in capacity Ratings (Items Nurher 3 Through 7) Since I.ast Report, cive Reasons:

None Power f.evel To Vhich TLeetricted, If Any (Net We): 280 9.

10. rusons for Restrictions, If Any:

Per corwitment to the NRC, long term operation above 85% power is pending comoletion of B-0 startup testing.

This Month Year to Date Cumulative 672 1,416 49,681

11. nours in Reporting rected 0.0 0.0 27,151.4 ,'

12. Nunher or sours Reactor was Critte.1-0.0 0.0 0.0 L 13. Reactor Reserve Shutdown soure 0.0 0.0 18,468.0

11. sours cenerator on-I.ine 0.0 0.0 0.0

15. Unit Reserve' Shutdova Hours -

0.0 0.0 9,861,714.4

16. cross Ther 1 rnergy cenerased (xwn) 0 0 3,248,594

17. cross tiectrie 1 znergy cenerated (Mwn)

-1,878 -3,895 2,924,063 is. Net rieetrie.1 energy cener.ted (Wa) 0.0 0.0 37.2

19. Unit s'ervice Factor 0.0 0.0 37.2

20. Unit Availability Factor 0.0 0.0 17.8

21. Unit Capacity Tactor (Using MDC Net) 0.0 0.0 17.8

22. Unit capact::y Factor (Using DtR, Net) 100.0 100.0 48.9

23. UnitroceesovesseRate 850301 through 24 Shutdowts Scheduled over :: ext 6 Msnths (Trpe, Date, and Duration of tach):

850415, 1104 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20072e-4 months <br />, Control Rod Drive Refurbishment.

E te shut Down at tad or Report Period, tstic.ated cace oc startup: 850416 25.

Torecast Achieved

26. Units In Test status (Prior to Coc=ercial operation):

N/A N/A INimr. CRITtCAt.trr N/A N/A INtrtAt. EttC nic m N/A N/A Coxxu C:A1. CFDATI0g

TSP-3 Att achment-3A Issue 2

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AVERAGE DAILY UNIT POWER LEVEL p Docket No. 50-267 Unit Fort St. Vrain #1 Date March 11, 1985 completed By Frank-Novachek Telephone (303) 785-2224 Month February, 1985 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net)

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1 0.0 17 0.0 2 0. 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 0.0 22 0.0 6

0.0 23 0.0 7

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 fUA 15 0.0 31 N/A 16 -0.0

• Cenerator on line but no net generation.

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REFUELING INFORMATION I I I l_1._ ?!ame of Facility l Fort St. Vrain Unit No.1 l 1 -

1 I l 2. Scheduled date for next l 4th Refueling: l l refuelieg shutdown. l February 1, 1986 l 1 - .

I I l 3. Scheduled date for restart l May 1, 1986 1 l following refueling. l _l i I I l 4. Will refueling or resumption ofl No l l operation thereafter require a l l l technidal specification change l l l or other license amendment? l l l l 1 l If answer is yes, what, in l ---------------- l l general, will these be?- l l 1 1 I l If answer is no, has the reload l l 1 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 1 l viewed safety questions are l l l associated with the core reload l l (Reference 10 CFR Section l l l

l 50.59)? l l l 1 l

l If no such review has taken l 1985 l l place, when is it scheduled? l l l l l

l S. Scheduled date(s) for submit- l l l ting proposed licensing action l ---------------- 1 l and supporting information. l l l

i I l 6. Important licensing considera- l l l tions associated with refuel- l 1 l ing, e.g. , new or different l 1 fuel design or supplier, unre- l ---------------- l l

l viewed design or performance l l analysis methods, significant l I l

l changes in fuel design, new l l l operating procedures. l I l l l

1 7. The number of fuel asscmbifes l l l

l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l spent fuel storage pool. I b) 143 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 1 l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueltag that can be dis- l and DE-SC07-791001370 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. l Comoany, and 00E.* l

• The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by 00E at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to acccmodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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public Service Company f OcEcadIn V .

16805 WCR 19 1/2, Platteville, Colorado 80651 )

March 15, 1985 Fort St. Vrain Unit #1 P-85078 Office Of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

REFERENCE:

Facility Operating License No. DPR-34

SUBJECT:

Monthly Operations Report-February, 1985

Dear Sir:

Enclosed, please find our Monthly Operations Report for the month of February, 1985.

Sincerely,

.Y$/

J. W. Gahm Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm s0 a,, 44s

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