ML20153C879

Monthly Operating Rept for Jan 1986

ML20153C879
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86018, NUDOCS 8602210685
Download: ML20153C879 (8)

Text

l -~-x PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 144 January, 1986 1

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8602210685 860131 PDR ADOCK 05000267

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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 January,1986.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The plant remained shutdown for Environmental Qualification throughout the month of January,1986.

The in-service inspection of the main steam and hot and cold reheat, and feedwater piping was completed. This testing revealed an indication in the hot reheat common header downstream of HV-2253 and HV-2254. This indication was ground out, rewelded, and post weld heat treated. There were six other minor indications found. They were blended out by grinding and did not require weld repairs.

Spent fuel shipping activities progressed smoothly.

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On January 22, 1986, while returning a clearance on "1D" helium circulator, a water ingress into the PCRV of approximately three hundred gallons occurred. Moisture removal efforts are in progress. Startup capability is expected in mid-February.

Work is continuing on the Environmental Qualification (EQ)

Program. We have completed as much work as is possible at the current time on all four helium circulators, with the remainder on hold for parts procurement. As of January 31, 1986, approximately thirty-eight percant of the Environmental y Qualification Station Service Requests (SSR's) generated to date have been completed. Another twenty-seven percent of the Station Service Requests are in progress. L 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 1D% OF THE ALLOWABLE ANNUAL VALUE None I I

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT l Attached l

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• e l rue 1 er 2 coruns: tex trot- :ccm sa. 50-267 cAn Februa ry 10. 1986 Com.t-a> rr Frank J. Novachek m trnant (303) 785-7224 ext. 201 C?tMTI*:0 STA*"S fiOTES

1. t=i: x,-e: Fort St. Vrain r

. Eersr:i=s ertoe: 860101 throuah 860131

3. Licensed ner=al r:ver (W:): 842

4. Nameplate Rating (Cress We): 342

5. Design I2eetrical 72:i=; (set We): 330

6. Maxi =.:n Dependable C :acity (Orcss We); _ 342

7. Mari=.=1 Dependable Capacity (Net We): 330 E. If Changes o: cur is Capa:ity r.atic;s (Ite=s Nu=ber 3 nrcugh 7) Since izst Repert. Cive Rtasens None

9. ro-er Level To '.~nich Restricted, If A=y (3e: We): 280

o. Rease=> rer res:rie: tons, it Aor: Per commitment to the NRC, long tenn operation above 85% power pending completion of B-0 startup testing.

This Posth Year to Late Ct.=ula tive

n. sours in reperti:s Period 744.0 744.0 57.769.0-

12. su=ter er sours neacter va, criticai 0.0 0.0 28,081.2

13. Reactor Reserve Shut =c Ecurs 0.0 0.0 0.0

34. P.ours Generatcr 0:-!.ine 0.0 0.0 18,468.0 _

15. r=it aeserve. shutdc. s Ecurs 0.0 0.0 0.0 2

16. cress n.er=a: tr..rc Cen rated <x,d> 0.0 0.0 9,895,083.2

17. Cross tiectrical I err. Genera:ed (C"d) 0.0 0.0 3,248,594.0 l a. re: ne:trical t=erre Generatee cua) -3,031.0 -3,031.0 2.893.242.0 s is. :=it service ractor .

0.0 0.0 31.9

c. t=i: Avai231:ity rac:or _

0.0 0.0 31.9

n. r=it capaci:7 ra:ter (:st=g a: xet) _

0.0 __

0.0_ 15.2

. :=it Capact:y rac:c (crits ::r. see) _

0.0 0.0 15.2

23. r=it rcreed onage 7. ate 100.0 100.0 58.3

~&. Shutd:v=s Scheduled Cr.er ::ex: 6 N r.ths (Type. Date, and Duratics er ta:h): NOne

5. :r shut :ca at tne er reper: reriod. rsti ated :cte or star:up: February 11, 1986 -

6. Units In Test S:att:.s (rri:r to Co nercial op ration): rare:ast Achieved

suut cuncntn N/A N/A

stun r tc r:ctre N/A _

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cc m ::n cr:n n es N/A N/A i

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TSP-3 Att achnant-3A C AVEnACE D.utY 1: NIT POWER LEVEL fssue2

, gg Docket No. 50-267 Unit Fort St. Vrain #1 Date' February -10. 1986 ,

Completed By Frank J. Novachek Telephone (303) 785-2224 lbnth January, 1986 DAY AVEFJGE DAILY POWER LEVEL DAY AVEP. AGE DAILY POWER LEVIL.

(MWe-Net) (!G'e-Ne t)

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1 0.0 17 .

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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

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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 0.0 16

• Generator on line but no net generation.

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_ UNIT sitUtlummS,jpj0WER RUIUgyg r... 7 r "' '

rucutt m. 50-267 unit nane

. Fort St. Vrain #1 DAre February 10. 1986 s

REroitt nostiii __ Januarf,1986 c0ter.zini st _ Frank J. Novachek _ , _ ,

, t a.r.rnoNe (303) 785-2224 fits 1 Hit? UF ~~ ~

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Ho. DATE TTrE LWH fRIRATION DFA50ff 5Y57Fil Crgr0rtENT REACTOR ff.R f CODE nmc 35-003851108 F 744.0 hr D CAlfSE AND CURflECTITP. ACT10ft 111 FREVEfff RF.CUR 2 N/A ZZ ZZZZZZ Environmental Qualification b

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• REFUELING INFORMATION l l l l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next .

1 I l ' refueling shutdown. I October 1, 1987 l l 1 I l 3. Scheduled date for restart l November 1, 1987 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l I operation thereafter require a l l l technical specification change l 1 l or other license amendment? l l l 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)? I l I I l

.I If no such review has taken l 1986 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 fuel des ign or suppl ie r, un re- l ---------------- l l viewed design or performance l l l analysis methods, significant l l 1 changes in fuel design, new l l l operating procedures. l l l

l l 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) 130 spent fuel elements l l

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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 licensed l Colorado, and General Atomic l l Capacity. l Company, and DOE.* l The 1992 estimated ce 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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Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 February 14, 1986 Fort St. Vrain Unit No. 1 P-86108 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 January, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

Sincerely, 7 /

J . Y.~ 7 3hm s Manepsr Nuclear Production Fort Lt. Vrain Nuclear Generating Station Enclosure cc: Mr. R. D. Martin Regional Administrator, Region IV JWG:djm

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