ML20090M687

Monthly Operations Rept,Apr 1984

ML20090M687
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1984
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84157, NUDOCS 8405290123
Download: ML20090M687 (9)

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PUBLIC SERVICE COMPANY OF COLORADO 1 FORT ST. VRAIN NUCLEAR GENERATING STATION f

b MONTHLY OPERATIONS REPORT NO. 123 i i

April, 1984 , .

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( This report contains the highlights of the Fort St. Vrain. Unit No.1, ac tivities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is for 1

the month of April, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1 The reactor was shutdown for the entire month of April. The primary activities included testing of equipment and components affected during the refueling outage, and maintaining plant

. conditions for the core support floor work.

The core support floor tube epoxy job, made difficult due to equipment problems, was completed. From all indications, the epoxy appears to have sealed off the leaking tubes. It is too early to tell if the overall job will be successful at operating conditions.

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The following tests were completed during April:

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1. The functional test of the Auxiliary Cooling Method i (ACM) generator. This unit was overhauled during refueling.

- .. 2. Overspeed test on 1A and 1C feedpumps. The units 1 'N w re overhauled during refueling.

l 3. The Loss of Outside Electric Power Tests. The 480V

essential buses w re upgraded and extensively changed j ,

during refueling.

4. The firewater pump capacity test. The pumps were overhauled during refueling.

5. Ultrafiltration unit performance test on condensate

cleanup. This unit was installed during refueling.

I Plant operation was also modified to allow clearances for reheat l . marmon flange replacement, core support floor epoxy, 440V bus

! testing, circulator outages, and auxiliary boiler work.

A complete plant valve lineup was performed and changes required to plant documents were noted. The process to revise the

! documents.is in progress.

Core orifice valves w re being partially stroked daily and core i

heating techniques were being utilized in an effort to return two orifice valves to operational status. The reactor vessel was depressurized to provide for replacement of an inoperable

. orifice valve with an operable one. All orifice valves w re O l.

operational for' equal flow positions by the end of this reporting period.

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-l Prestressed Concrete Reactor Vessel tendon surveillance l l activities continued throughout the month, including Itft-off l l testing and inspection of vertical and bottom head tendons. One i l vertical tendon was detensioned to provide for further l Inspection and two of the wires were pulled to allow for  ;

l 'motallurgical and engineering evaluation. Further detensioning l and inspection will continue in support of the overall analysis c l iflorts.*

t halstore removal from the Prestressed Concrete Reactor Vossel is G '

in progress, bist the present high levels have been predicted to j- extend the c 4 age through May 28, 1984.

2.0 SINT.E RELEASES OF RADI0 ACTIVITY OR RADIATION EXp0SURE IN EXCESS FT0XdF'TiiE AR6WABMThiftI4LTKWf .

None.

3.0~ INDifATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEt, EiA41NAT.I_D.N None.

4.0 MMTHl.YOPERA}lNGDATAREFORT Attached. .

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Revised 5/18/81 to reflect April activities only, i

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. , tum a ortnartwo nm uroar x ctrr so. 50-267 Dar May 8, 1984 COMPLETED 37 Chuck Fuller trLarnowc (303)785-2224 ,

OPERATIM ITMUB infts

1. omit nese Fort St. Vrain .

2. neverties perudi 840401 through 840430

3. Liseemed Thereal Power Oest): 842 4 seenstete settaa (creu sese): 342

3. Duise untrical nettes (not sese): 330

s. Nestam Dependable caputty (ame sese): 342

f. hastase Dependable caputty (not lese): 330

s. If Cheapes oesw to cepeetty mettese (1 tees thenber 3 thromen r) stase last neport. Gave nessees:

None j s. rever Lent te asen teatruud. If aer (ma inse), 280

10. nessem for nutetenues. If my, Per comitment to the NRC, long tem operation above 85% power is pendino completion of B-0 startuo Testing.

The meta teor te new c . 44tt,e n noen ta ne,erstes pated 719 2.903 42.384

12. sweber et newe nauwe use crittul 0.0 -- 468.0 26.295.3 ,'

u. neester neeem simedan seen 0.0 0.0 0.0

16. new seeseewe on uae 0.0 446.6 18.249. L

u. cast neeer,e shnasee now. 0.0 0.0 0.0 1s. oren ther=1 sursy seemted use) 0.0 240.818.8 9.762.136.4

17. orou nestrtui amery e eenad one) 0 77.41? 3.?30.862 1s. ha untraut neersy e eerned (ine) -2.507 64.924 2.936.454

18. Dett seretee ru ter 0.0 15.4 43.1

20. Dett metlebuter ruwe 0.0 15.4 43.1

n. unit ce,asw ruwe (getes ese mt) 0.0 6.8 21.0

22. Dett ce,utty ruar (setes sea not)

O.0 6.8 21.0

u. tets reeeed on new 0.0 1.5 38.9

n. swideem sene4. led owe men a metne (tr,e, hu, sed Dweisee er seen): 5-1-84 through 5-28-84, l primary coolant cleanup following shutdown, 672 hours0.00778 days <br />0.187 hours <br />0.00111 weeks <br />2.55696e-4 months <br />,10-19-84 through 11-10 84,

u. 1Y[ se EteNeNJ: N.obted Date of stereepi 6-16-94 4 H. Dette 1. Test statw (priot to ceaneret.1 opeestau): Pereuet Ashio,e4 1N!T1AL cut CALI17 N/A N/A twtrtALLscructti N/A N/A coissac 4L oranArrow N/A _

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, Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date May 8, 1984 Completed By Chuck Fuller )

Telephone (303)785-2224 Nonth April 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 0.0 17 0.0 l l

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 13 . ' O.0 29

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

• Generator on line but no net generation.

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REFUELING INFORMATION I I I l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l l 2. Scheduled date for next l 3rd Refueling: l 4th Refueling:l l refueling shutdown. I currently underway l Feb. 1, 1986 l l l l 1 l 3. Scheduled date for restart l May 28, 1984, l May 1, 1986 l l following refueling. I 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> l l l 1 I I l 4. Will refueling or resumption ofl No l No l l operation thereafter require a l l l l technical specification change l l l l or other license amendment? l l l l l l l l If answer is yes, what, in l ---------------- l ------------ 1 l general, will these be? l l l l l l l l If answer is no, has the reload l l l l fuel design and core configura-l l l l tion been reviewed by your l l l l Plant Safety Review Committee l ---------------- l No l l to determine whether any unre- l l l l viewed safety questions are l l l l associated with the core reload l l l l (Reference 10 CFR Section l l l l 50.59)? l I l l l l l l If no such review has taken l ---------------- l 1985 l l place, when is it scheduled? l l l l l l l l 5. Scheduled date(s) for submit- l l l l ting proposed licensing action l ---------------- l ------------ l l and supporting information. l l l l l l l l 6. Important licensing considera- l l l l tions associated with refuel- l l l l ing, e.g., new or different l l l l . fuel design or supplier, unre- l ---------------- l ------------ l l viewed design or performance l l l l analysis methods, significant l l l l changes in fuel design, new l l l l operating procedures. l l l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l 1482 HTGR fuel elements l l spent fuel storage pool. I 251' spent HTGR fuel elements l

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REFUELING INFORMATION (CONTINUED) l l 1 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 elen,ents).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. I Company, and DOE.* l i

• 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 off Odemde y V .

16805 WCR 19 1/2, Platteville, Colorado 80651 i

May 22, 1984

Fort St. Vrain Unit #1 P-84157 Office of Inspection'and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission

Washington, D.C. 20555 l

Reference:

Facility Operating License

! No. DPR-34 Docket No. 50-267

Dear Sir:

! A portion of the Monthly Operations Report for the month of

{ April , 1984, inadvertently discussed plant activities that were 2

actually initiated in early May, rather than during the month of April. Enclosed, please find a revised report, with the revised portion identified.

1 j Very truly yours, i

i 5

Don Warembourg 4

Manager, Nuclear Production Enclosure

-cc: Mr. John T. Collins DWW/djm 4

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