ML20210C117

Monthly Operating Rept for Aug 1986

ML20210C117
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86551, NUDOCS 8609180248
Download: ML20210C117 (7)

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.. g PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 151 August, 1986 i

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, 8609180248 860831

PDR ADOCK 05000267 j

R PDR ((dY it, l'

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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 August, 1986.

I- 1.0 NARRATIVE SUMARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE

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, The reactor remained shutdown during the entire month of August for Environmental Qualification modifications. ,

On August 5, 1986, a meeting was held between Public Service Company and Region IV to discuss the Systematic Assessment of Licensee Performance (SALP) Report for.the period March 1, 1985 through May 6, 1986.

On August 5-6, .1986, .the annual Fort St. Vrain Radiological j

Emergency Response Plan exercise was conducted.

L Three items were identified requiring reports to the Nuclear i Regulatory Commission. These are: LER 86-023, Radiation

! Monitors Found Out of Calibration; LER 86-024, PCRV Rupture Disc Found Out of Tolerance; and LER 86-025, Reactor Building Sump Release Not Continuously Sampled.

Hot Service Facility decontamination has been completed and preparations for reflector block shipping are in progress.

Security improvements appear to be on schedule with the exception of one area which is expected to require approxmately three months in addition to the original schedule.

l On August 24, 1986, primary coolant circulation was switched from

, Loop I to Loop II. Environmental Qualification modifications are l now proceeding on Loop I.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE I

None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS i

None

, 4.0 MONTHLY OPERATING DATA REPORT .

5 l  ; Attached i

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Attecarcat-32 Irse. 2 Page 2 sf 2

- o=mn=n Arson- mes:r s. __50-267 nr.z Sentomhpr 4. 1QRA Cc::r:.r: n :: F. J. Novachek tzt.zrnos: (303) 620-1007 ermn= s.A. s so::s

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1. ne:s : Fort St. Vrain Unit No. 1

2. n,por:ing 7.rs.d: 860801 throgh 860831

s. n e.a.d Therna: > = r (m :): 842

4. Nameplae. na:ing.(Gre.s W .): 342

s. suis = n c:rical marias (s.: s.): 330

s. x==1=== nerendahl. ca city (crew w.): 342

7. Maximu= Dep.=dahl. capaci:7 (s.: s.): 330 .

8. If Csang.s Occur in capacity natings (Items Nuno.r 3 3 rough 7) since las Report. civ.1.asons:

None

f. Power L v.1 To Thich 1. strict.d. If Any (l3.s W.): 0.0

o. reasens for an:r:.ezions. If A. 7: per enmitment to the Nuclear Ronnlatnev en-m4ce4an remain shutdown pending completion of Environmental Oualification modifications.

This Meath T ar t. Dat. Cu=ulative u . no rs in saportins 7.rted 744.0 5,831'.0- 62,856.0

12. su=her er neurs an.ewr was criticai 0.0 3.456.6 30.537.8 3

3. auetar amerve sha:down nour 0.0 0.0 0.0

24. neurs c. utor on-un. 0.0 1,087.1

• 19.555.1

15. cr.it m...rv. sha:d.vn n.=s n.n 0.0 0.0

16. crou n.rma: rurar .naras.d c (: sis) nn 370,316.6 10.255.300.R

. .17. crus n.cerical zo.rsr c s. rated (su) nn 85,402.0 3.333. con.n i

la. s.1 n e rica za. gy c. us.d (su) -2.248.0 58,926.0 2,955,199.0

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s. cr.1: s.rrice rac:. . 0.0 18.6 31.1

. t=A: avanahi ::7 rae:or 0.0 18.6 31.1 14.2

1. cais cap.es:7 rector (tsin xac z. ) 0.0 3.1

22. Tair capacity Tactor (Using DE1 3.t) 0.0 3.1 14.2

23. ratt rare d o. case mat. Inn.n 81.4 60.4 j

s. shutdow sch.eul.a over ser: 6 mn:hs (?fpe, nat., ame curant n of Zach): Environmental Oualification modifications. 860901.1160 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.4138e-4 months <br /> j :s. :f the amm at saa of seper: p rise. rs:1:a: e sa:. of star:v, December 31. 198_6 l

26. Units := Test statua (Frior to co mer:ial operation): rare:as: Achieved l

=nn ex:nen:n N/A N/A Innn rac t:c:n N/A N/A cc. 2xc:r. crmnes N/A N/A

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267-Unit Fort St. Vrain Unit No. 1 Date September 9, 1986 Completed By F. J. Novachek Telephone (303) 620-1007 Month. August DAY AVERAGE DAILY POWER LEVEL -DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.0 17 0.0

2 0.0 18 0.0 3 0.0 19 0.0 il 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 13 0.0- 29 0.0 i

14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

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• Generator on line nut no net generation.

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i TSP-3 Attachment TSP-3C Issue 2 Page 1 of 1 .

UNIT SHUTDOWNS AND POWER REDWTIONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra in Un i t No. 1 DATE September 8. 1986 COMPLETED BY Frank J. Novechek TELEPHONE f3031 620-1007 REPORT MONTH Auaust. 1986 i HETH00 0FI I i l SHUTTING I l CAUSE AND CORRECTIVE ACTION I l No. DATE l TYPE DURATION REASON DOWN LER E SYSTEM COMPONENT TO PREVENT RECl8RRENCE I l

l REACTOR CODE CODE l l i l i I

86-03 860801 1F l 744 hr D 1 i N/A ' ZZ ZZZZZZ l Environmental Quallrication I modifications 1 I I I I I I I I I I I I I i 1 I i

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I I I I l I I I I I l' I i 1 I I I I I l I ll 1 1 I I I

' I I I I i 1 I I I I l t 1 I I I I I I i 1 l I I i I i I f I I I I I I I I '

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I i i l I i l I i i i i l i i I l 1 1 I I I I

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I I I I i i I I I I I I 1 i i i i l l I I I I i 1 1 I I I I I I I I i 1

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REFUELING INFORMATION l 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 l l refueling shutdown. I March 1, 1988 l l l l l 3. Scheduled date for restart l June 1, 1988 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 1 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 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

. 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 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 7. The number cf 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) 0 spent fuel elements l

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. .m REFUELING INFORMATION (CONTINUED) i 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 1 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 .

I charged to the spent feel 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.

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PublicService . . . . .

Company of Colorado

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16805 WCR 19 1/2, Platteville, Colorado 80651 September 15, 1986 Fort St. Vrain Unit No. 1 P-86551 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 - AUGUST, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

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

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

Sincerely, J. W. Gahm Managar, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure  ;

cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm ZE H 4I