ML20101A910

Monthly Operating Rept for Nov 1984

ML20101A910
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1984
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84519, NUDOCS 8412190414
Download: ML20101A910 (8)

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__s PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION s'

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MONTHLY OPERATIONS REPORT NO. 130 November, 1984 0

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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 November, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Our new Power Plant Maintenance Information System (PPMIS) was put into service on November 5, 1984, and after a month of operation, most of the initial problems have been resolved.

, After everyone becomes more familiar with this system, it should become a very important operating asset. N~

Construction has installed a new flow totalizer in our main tower blowdown line. This should give us a better indication of water chemistry requirements, and make it easier to maintain proper circulating water chemistry.

Contractors working on the sewage lagoon dug up a 13KV feed cable from Bus 7 to various users, including the Visitor's Center and the Fort St. Vrain River structure. The Security Department maintained catalytic heaters in various areas to keep pipes from freezing. The cable has been repaired and returned to service.

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"1A" Purified Helium Compressor Motor Generator Set failed on Thursday, November 1, 1984. Maintenance and the Electricians were successful in repairing the compressor and returning it to service.

Clearances were removed from "B" Helium Circulator, and after flushing of the bearing water piping and warm up of the steam piping, the circulator was brought up to speed. The Inside Auxiliary Boiler was placed in service parallel with the outside boiler to attain the maximum circulator speed and helium flow.

This, as expected, showed a rise in primary coolant moisture.

However, after only a few days, the primary coolant moisture level reversed, to a downward trend.

The bearing water pump for Loop II, P-2102-S, had a bad seal.

This pump is necessary to operate Loop II circulators, because one other Loop II bearing water pump is inoperable. Since Loop I Heliumi Circulator, "1B", is operable, Loop II was shutdown and the bearing water pump repaired.

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Tse-3 Attachment-3B

• Issum 2 ortamsc Dm upon pocm m. 50-267 nut December 7, 1984 caetz:Ep af Frank Novachek mxrmat (303) 785-2224 ormTrso STATUS mo m

1. anit m.=: Fort St. Vrain .

2. a portins Period 841101 through 841130

3. uc ed Thermal rouer (me): 842

4. Nameplate Rating (cross We): 342

5. Dosisa nectrical natins Diet me): 330 342 ' ~

6. **== Dependable capacity (cross We):

7. hd== Dependable capacity Diet We): 330

8. If changes occur in capacity Astings (1tems umber 3 Through 7) Since Last Report, cive Beesons:

None

9. Power Level To Which Eastricted, If Amy Olet We): 230 lo. aamsons for a tricts . If any: Per cocynitment to the NRC, long tenn operation above 85% power is cendin9 completion of the B-0 Startup Testing.

This Meath Year to Dato cimaalative

u. nours in n portins Pert.d 720 8,040 47,521

12. number of nours ameter v s critte.1 0.0 1,324.1 27,151.4 ,

u. n=ccer anem shutd n sour. 0.0 0.0 0.0

14. now. cementor on-um 0.0 660.1 18,463.3

15. onit me>e m shutdown Eeur. 0.0 0.0 0.0

16. om . Th rmal no.rsy c rat.d osa) 0.0 340,407.9 9,861,725.3

17. cross Electrical Imery anaerstad Osm) 0 91,544 3,248,594

, 1s. net nectrical iserer ca ret.4 osa) -2803 58,889 2,930,419 I

19. Unit s'ervice rector 0.0 , 8.2 38.9 2o. unit Availab nity Factor 0.0 8.2 38.9

21. omit capecity raetor (usins oc met) 0.0 2.2 18.7

22. Unit capacity rector (usins nem met) 0.0 2.2 18.7

23. unit rorced oucas nate 100.0 85.6 45.7

24. Shutdowns Scheduled over Next 6 haths (Type Date, and Duration of Each): 12/01/84 throuch 03/31/85,2904 hours0.0336 days <br />0.807 hours <br />0.0048 weeks <br />0.0011 months <br />, Control Rod Drive Investigation.

25. If Shut Down at End of asport Period. Estimated Date of Startup: 04/01/85 4

26. Units In Test Status (Frior to comercial operation): Forecast Achieved InTut cuncAun N/A N/A

xInAL ELEemem N/A N/A comascuL ormnos N/A N/A I

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.* . Attcchment-3A i AVERAGE MILY UNIT POWER LEVEL hm2 l Pcge 1 of 1 l Docket No. 50-267 Unit Fort St. Vrain Date December 7, 1984 Completed By (303) 785-2224 Telephone _

Nonth November, 1984 -

MY AVERAGE MILY POWER LEVEL MY AVERAGE MILY POWER LEVEL (We-Net) (We-Net) 1 0.0 17 0.0 9

2 O.0 18 0.0 3 0.0 19 0.0 j 4 0.0 20 0.0 1

} 5 0.0 21 0.0 6

0.0 22 0.0 0.0 0.0 7 23 8 0.0 24 0.0 9 0.0 25 0.0 -

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! 1o 0.0 26 00 I

j 11 0.0 27 0.0 1

12 0.0 28 0.0 13 0.0 29 0.0 i.

14 0.0 3o 0.0 15 0.0 31 N/A l

16 0.0 l

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REFUELING INFORMATION I l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l 4th Refueling: l l refueling shutdown. l February 1, 1986 l l 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 l l 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 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 1985 l l place, when is it scheduled? l 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 f u e l de s '. g n c r s up p l i e r , u n re- l ---------------- l l viewed design or performance l l l

analysis methods, significant l l changes in fuel design, new l l

,l' ll operating procedures. l l l ~ l l ~

l 7. The numbe'r 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) 143. spent fuel elements l _ _ _

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REFUELING INFORMATION (CONTINUED) l l l l 8. The present licensed spent fuell 1 l pool storage capacity and the l 's 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 w I 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 accomodate eight fuel segments. It is

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

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PLIblie SerVICO (OttipanV T CEOGIfSdI@

V 16805 WCR 19 1/2, Platteville, Colorado 80651 December 11, 1984 Fort St. Vrain Unit #1 P-84519 Office of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

REFERENCE:

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

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of November ,1984.

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Sincerely,

/ J. W. Gahm Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm 7EA II m es q;l>

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