ML20099H146

Monthly Operating Rept for Oct 1984

ML20099H146
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1984
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84490, NUDOCS 8411280040
Download: ML20099H146 (10)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 129 October, 1984 9Y e/

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l 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, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.0 STATION OPERATIONS The Nuclear Regulatory Commission inspectors were on-site this month, testing the Operations staff on Radiological Emergency Response knowledge. They were very satisfied with the results.

Helium Circulator "1C" was successfully returned to service after installing a change to the high pressure separator drain. The circulator is being driven by auxiliary boiler steam at approximatel , 5000 rpm to maintain primary coolant flow at acceptable levels for present conditions.

We began pressurizing the reactor to aid in cleaning up the primary coolant. This increased pressure allowed the normal usage of the helium purification system. We then received permission from the Nuclear Regulatory Commission to exceed 100 psig primary coolant pressure. The secondary covers and circulator interspaces were all returned to normal service and on Thursday, October 4, 1984, the PCRV was pressurized to approximately 140 psig. After receiving a helium shipment, the PCRV was pressurized to 150 psig, the core support floor was returned to no rmal , and the secondary coolant flow was terminated to allow primary coolant to heat up and facilitate moisture removal.

Primary coolant flow is being maintained by a helium circulator driven by cold reheat steam from the 150 psig header. This steam then circulates through the steam generator reheaters and adds heat to the primary coolant.

The Change Notice which routes the high pressure separator drain line to the bearing water surge tank is completed on Loop 1. The Functional Tests will be completed when adequate bearing water pumps are available, and the system can be returned to service.

i On October 18, 1984, "B" purification train was plugging up due to moisture. The regeneration dryer was regenerated, and 30-35 gallons of water were drained from the knockout pot.

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On October 20, 1984, a valve section breaker burned up in a

- turbine motor control center (TMCC) and caused the loss of one of the auxiliary boilers. The boiler could not be immediately restarted, and primary coolant flow was terminated for approximately four hours due to the lack of-steam. The other auxiliary boiler problem was traced to a bad igniter.

On Tuesday, October 23, 1984, primary coolant flow was shutdown to repair the bearing water surge tank makeup pump, P-2105. This outage lasted approximately four hours.

The procedure was developed for the stuck control rod drive inspection, The control rod drive has had the inspection windows and the failed cable, as well as its sister cable, removed. The rods have been resuspended using new cable. .

that was swaged to the remaining cable, and the control rod drive has been moved to an equipment storage well. A continuing analysis of the cable failure mechanism is in progress. The cable pieces have been sent off-site for

, analysis.

The "1A" helium circulator tests concluded that a bearing water to interspace leak does exist in "1A" helium circulator. The system has been returned to normal and Loop 1 has been shutdown and isolated for other activities.

The control rod drives that have been removed from the reactor are in the process of being refurbished in the Hot Service Facility.

The hydraulic helium circulator removal unit has been removed and sent off-site for repair. When returned, the removal and replacement of "1A" helium circulator will

, start.

i The regeneration section of the helium purification system has had the regeneration compressor overhauled. When problems persisted, a section of line was removed, and the laminar flow element had displaced downstream. Search for a new flow element is being conducted.

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I 2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS

,OF 10% OF THE ALLOWABLE ANNUAL VALUE None.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION None.

4.0 MONTHLY OPERATING DATA REPORT Attached.

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Attachma t-D

'* Issue 2 orru m e m TA azroar Docur zo. 50-267

- mTr November 14, 1984 court.rnD nr Frank Novachek Tnzymost (303) 785-2224 OPDATDiC STATt3 sons l

1. nate me : Fort St. Vrain .

2. saportins teriod: 841001 throuah 841031

3. ne d th.r=1 rever oere): 842

4. Nameplate Ratins (Gross Nie): 342 .

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5. Desisa nectrical natins olet lese): 330

6. W- Dependable capacity (Groes seie): 342

7. Naziam Dependable capacity olet lese) 330

4. tr changes occur is capacity Eatings (Items Number 3 Through 7) Since last Report, Give Beesoas None

s. Power imi To ubich Retricted, If Any (met 3Sie): 280

10. a =om for a eurtect.=, ir any:

PSC commitment to the NRC, long term operation above 85% power is pending completion of the B-0 Startup Testing.

This Meath Year to Date cumsalative n . a.ua is neportins peri w 745 7,320 46.801

12. n=ber er neun meneter was crittui 0.0 1,324.1 27.151.4 ,"

13. noneter muerve Shetdeva no n 0.0 0.0 0.0

14. nours cemrator On-use 0.0 660.1 18,463.3

15. cast neserve Shutdown Bours 0.0 0.0 0.0

16. cron Thermal zeerer cour t.d osa) 0.0 340,407.9 9,861,725.3

17. cron neetrical snersr cement.d one) 0 95,144 3,248,594 1s, not nectrie 1 zeersy comat.d use) -2,678 61,692 2,933.222

19. voit s'ervice r.ecer 0.0 9.0 39.5

20. omit Avanannity rector 0.0 9.0 39.5

21. onit capeesty r.ecor (notas noc not) 0.0 2.6 19.0

22. omic capeetty r.eter (n ins esa not) 0.0 2.6 19.0

23. mit Forced Out., mate 1.00.00 82.8 44.5

24. Shutdowns Scheduled Over liest 6 thaths (Type, Date, and Duration of Esah): 11/01/84 throuah 03/31/85, 3624 hours0.0419 days <br />1.007 hours <br />0.00599 weeks <br />0.00138 months <br /> Control Rod Drive Investigation.

25. 1 Shut Dove at sad of asport Period,1stimted Date of Startup 04/01/85 4

26. onics la Test Status (Prior to Commercial Operation): rotecast Achieved ixinAx. cuncAun N/A N/A isznAI. nzerucm N/A N/A aneiracIAI. OPERAnos N/A N/A

TSP-3 Attcchment-3A AVERAGE MILY UNIT POWER LEVEL 288 2 p

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Docket'No. 50-267 Unit Fort St. Vrain Date November 14, 1984 Coupleted By Frank Novachek Tele % e (303)785-2224 Month October, 1984 -

DAY AVERAGE MILY POWER LEVEL MY AVERAGE MILY POWER LEVEL (We-Net) (We-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

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13- 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 _

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, REFUELING INFORMATION

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~ l 1. Name of Facility Fort St. Vrain Unit No. 1 l-l- .

l l 2. Scheduled date for next l 4th Refueling: l l refueling shutdown. I February 1, 1986 l 1 l l l 3. Scheduled date for restart l May 1, 1986 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

1 l l l If answer is yes, what, in l ---------------- l l general, will these be? I l 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 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 t

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

I l l j l 5. Scheduled date(s) for submit- l l j l ting proposed licensing action l ---------------- l l and supporting information. l l l l l l 6. Important licensing considera .I l l tions associated with refuel- l l 1 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 1 l 7. The number of fuel assemblies l 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) 143 spent fuel elements l 4 -,

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REFUELING INFORMATION (CONTINUED)

I 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 1 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. l 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 accomodate eight fuel segments. It is

!-- estimated that the eighth fuel segment will be discharged in 1992.

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. Public Service Company T Osando y 16805 WCR 19 1/2, Platteville, Colorado 80651 November 14,'1984 Fort St. Vrain Unit #1 P-84490 Office of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

REFERENCE:

Facility Operating License No. OPR-34 Docket No. 50-267

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of '

October, 1984.

Sincerely, Nth J. W. Gahm Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm

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