ML20207C735

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Monthly Operating Rept for June 1986
ML20207C735
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/30/1986
From: Gahm J, Novachek F
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86458, NUDOCS 8607210427
Download: ML20207C735 (8)


Text

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 149 June, 1986

8607210427 860630 7 QF f j PDR ADOCK 0500 /

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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 June,1986.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown during the entire month of' June for Environmental Qualification modifications.

A test was run on "1D" Helium Circulator static shutdown seal to evaluate seal integrity. The results indicated that the seal was successfully set.

On June 3,1986, a third party audit of the low level radioactive waste handling and transportation program was performed by Nevada Inspection Services. No problems were identified.

On June 13, 1986, clearances were hung on the circulating water system, resulting in the pump pit being inadvertently flooded.

All affected motors were removed for repair and inspection.

.) On June 25, 1986, a Radiological Emergency Response Plan dress rehearsal was held for personnel training / evaluation.

Quarterly preventive maintenance inspections were completed on emergency diesels K-9205X and K-9206X, with no problems noted.

Overall Environmental Qualification Station Service Request work is ahead of schedule. It is anticipated that "D" Helium Circulator work will fall behind schedule due to parts availability for Change Notice work.

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 EXAMINATIONS None 4.0 MONTHLY OPERATING DATA rep 0RT

, Attached i

A::SC.73'cr. = 33 Issu. 2 ormn= ex A mor- noc;;= r.a. 50-267 3:: June 10, 1986 c::cr_t c : Frank J. Novachek n _ rses: (303) 785-6471, ext. 201 errun= m.s so: s

1. re: x : Fort St. Vrain, No.1
. a.;:r.as r.u.e: 860601 through 860630
2. uuu.e Ther=a: rever (5:): 842 4 Kam. plat. Rating (cress W.): 342
5. e
  • sig: n.=:rizal ta:ing (s.: p.): 330
6. *>s-- ney.ndabl. casacity (cross W.): 342
7. P.ar'-- nep.sdahl. capacity (:;.: 5.): 330 .

3 2. rough 7) sine. Las: 1. port. civ. 1sa..=s

8. If Chang.s 0::c i= capacity 3atings (It =s Nu=b.

None

s. r=w r Lev.1 Ts n.ich Eastricted. U Any (r.e: s.): 0.0 i
o. sauens ter w:rtenou. n A y Per connitment to the NRC, remain shutdown pending comoletion of Environmental Qualification modifications.
This Month Tsar s. D.3. cuculative n . m a n in a. , r u ng 1.ri.4 720.0 4.343.0 61,368.0
12. ==>.: .e m es a= cur su criucaz 0.0 2,456.6 30,537.8
s. w e:=r w erve ss.:4.vm m or. 0.0 0.0 0.0
25. newsc. uuron-u 0.0 1,087.1 -

19,555.1

15. re: nuen. m:4== neurs 0.0 0.0 0.0 Is. crou n.rma: rara c.= ras.4 css) 0.0 320.316.6 10,265.399.8
17. crus n.cerical z..ruc . nud os.i> 0.0 85.402.0 3.333.996.0 1s. s.: n. rical z=re c.=ne.4 (s.3) -2.537.0 63,389.0 2.959.662.0

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s. te: s.rrie recur . 0.0 25.0 31.9
20. tai: Avanan ni:7 recur 0.0 25.0 31.9
n. tai: capac1=y factor (cs1= une s.3) 0.0 4.4 14.6
n. tait cap ci:7 racter (using nr1 see) 0.0 4.A 14.6
s. tait fore.4 o.cas. aa n 100.0 75.0 50.1
s. shu:4,v== sch.4u:.4 ov.: s.x: s mn:hs (efp., n.:., .ne Dura 1. er zach): Environmental Oualification modifications. 860701. 1976 hours0.0229 days <br />0.549 hours <br />0.00327 weeks <br />7.51868e-4 months <br />.

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5. :t m : n vn se tr.4 et a.por: P. rise. ta n=,see 4:. of scar:u,: Seotember. 21. 1986 .

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6. Units In T.se $:stu.s (rrior to co ==.rtial Operation): For.cas: Achieved

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. Attachment-3A AVERAGE DAILY UNIT POWER LEVEL s 2 p

Docket No. 50-267 Unit FSV#]

Date June 10, -1986 completed 3y Frank J. Novachek Telephone (303) 785-6471, ext 201 Month June. 1986

  • DAY AVERAGE DAILY POWER LEVEL DAT AVERAGE DAILY POWER LEVE:

(We-Net) (We-Ne t)

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1 n_n 17 0.0 2 n. 18 nn

  • 3 0.0 19 nn -

4 n.n 20 0.0 5 nn 21 0.0 6 nn. 22 0.0 7 0. 0~ 23 0.0 8 0.0 24 n.n 9 0.0 25 nn 10 0.0 26 0.0 11 nn 27 0.0 12 nn 28 0.0 .

13 0.0 29 0.0

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14 0.0 30 n_n 15 0.0 31 N/A 16 0.0

  • Generator on line but no net generation.

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9 REFUELING INFORMATION I I I l 1. Nane of Facility l Fort St. Vrain Unit No. 1 l l 1 l l 2. Scheduled date for next l l l refueling shutdown. I March 1, 1988 l l l 1 l 3. Scheduled date for restart l June 1, 1988 l l followino refuelino. 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 l l If answee is no, has the reload l l 4

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 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 1 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 1 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 coerating procedures. I l l 1 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 soent fuel storage ocol. I b) O scent fuel elements l l

l i

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REFUELING INFORMATION (CONTINUED) l I 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).1 l planned, in number of fuel l No change is planned. l l assemblies. l l l i 1 l 9. The projected date of the last l 1992 under Agreements AT(04-3)-6331 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.

r h Public Service ~ ==f,;;'ta. .

16805 WCR 19 1/2, Platteville, Colorado 80651 July 11, 1986 Fort St. Vrain Unit No. 1 P-86458 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 June, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

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

Sincerely, .

1 J.

N. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station l l

Enclosure l

cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm

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