ML20098D676

Monthly Operating Rept for Aug 1984

ML20098D676
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/31/1984
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84352, NUDOCS 8409270697
Download: ML20098D676 (9)

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

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MONTHLY OPERATIONS REPORT NO. 127 August, 1984 ',

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This report contains the highlights of the Fort St. Vrain, Unit

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No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is for '

the month of August, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY ,

RELATED MAINTENANCE l

l The control rod investigation continues. In order to expedite

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primary coolant moisture removal, the control rod drives from i several regions have been placed in the equipment storage wells and have been replaced by temporary spare rods. This allowed ,

pressurizing the PCRV to approximately 90 psia so that the  ;

helium purification train could be placed in service on ,

August 8, 1984.

The commitment made to the Nuclear Regulatory Commission to i refurbish both the gear train and shim motors on the six control red drises that did not scram on June 23, 1984 has been completed.

The seventh control rod drive had a bad shim motor. The motor stator was replaced, and the rod was reassembled, but the scram time was near the limit. It was decided to refurbish the gear train assembly. The gear train assembly has been refurbished, but the control rod drive lifting cable is partially frayed.

C,.s, The rod drive cannot be utilized unless the control rod cable is replaced.

The control rod drive in Region 7, which had a slack cable indication, was prepared for removal from the core. The removal process was nearly completed when it was discovered that one of the control rod drive absorber strings was not fully retracted.

The string was bent and could not be returned to the core so the control rod drive could not be released from the auxiliary tr.ansfer cask. Preparations are in progress to prepare the Refueling Floor for removal of the control rod in an abnormal configuration. Upon completion of this task, control rod drive refurbishing and repairing efforts will continue per commitment to the Nuclear Regulatory Commission.

Loop I was placed in service August 7, 1984, to maximize primary coolant flow for this moisture removal operation.

Due to the abnormal control rod configuration, in-core control rod drive testing has been slowed because the core reactivity status must be confirmed making neutron diffusion computer code runs for each evolution.

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({\ A significant number of Maintenance personnel from the Denver area have been assigned to Fort St. Vrain temporarily to perform maintenance activities which were not being performed due to the control rod drive work.

A Nuclear Regulatory Commission inspection team was on site the week of July 30 to monitor control rod drive work activities.

The annual Radiological Emergency Response Plan (RERP) drill was performed on August 15, 1984. Problems were experienced with the notification fan-out procedure, but operational response to the situation went well.

Spent fuel shipping continues. Several loads have been sent off site this month.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 0F,10% OF THE ALLOWABLE ANNUAL VALUE None.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION None.

(bh 4.0 MONTHl.Y OPERATING DATA REPORT Attached.

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- :57-3 Attlehnent-35 Iseus 2 1 Pep i cf i 1 orru Isc m:A nuor- Docart no. 50-267 l mn September 12, 1984

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cmeuuD at Frank Novachek l rnrraour (303) 785-2224  !

oPERAMNC STATUS _

lnoirs

1. onic s : Fort St. Vrain .

2. n.portins reries: 840801 through 840831

3. ucemw Themal Po osts): 842

4. Nameplate natins (cross We): 342 5 .' D. sign nectrical natins olet me): 330

6. Maximm Dependable capacity (cam asie): 342

7. m w- D.pendable c.peesty (n.: isae): 330 1

8. If Changes occur in capacity Batings (Items Number 3 Through 7) Since last Report, cive Beasons:

None

9. rever level to n ich triced . If Amy (u.c m .): 280 lo. naasons for nu trictions, If my: Per consnitment to the NRC, long term operation above 85% power is pending completion of the B-0 Startup Testing.

This Meath Year to Date Cumulative

n. nour. in n.portins Period 744 5,855 45,336

12. mmber of a r. menetor uns critica1 0.0 1,324.1 27,151.4 ,"

-13. n=ctor n erve sha 4.ua neers 0.0 0.0 0.0 14 nours c unter on-use 0.0 660.1 18,463.3-

15. Unit muerve shuta nour. 0.0 .0.0 0.0

16. crom Themal znersy c new osa) 0.0 340,407.9 9,861,725.3

17. cron n.e rical mnerar cemented osa) 0 95,144 3,248,594 is not nutrical za.rar can r tw osa) -3,571 66,790 2,938,317

19. Unit s'e rsies Factor 0.0 11.3 40.7

20. mit A milahnity rector 0.0 11.3 40.7

n. onit capuity rutor (usins unc m t) 0.0 3.5 19.6

22. Unit capacity Fator (using nun u.t) 0.0 3.5 19.6

23. mit rorew outa s nat. 100.0 72.3 41.9

24. sh=4 s scheduled over mest 6 inachs (Type, Date, and Duration of ameh): 9-1-84 throuah 11-1-84, ,

1464 hours0.0169 days <br />0.407 hours <br />0.00242 weeks <br />5.57052e-4 months <br />. Control Rod Orive Investiaation.

25. If Shut Down at End of asport Period. Estimated Date of startup: 11-1-04 1E

26. Units In Test Status (Prior to Commeretal operation): Forecast Achieved I IsInn exIncnIn N/A N/A IxInn nzerticm N/A N/A comzRCIn oPERAnON N/A N/A 4

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. Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL D"2

. Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date September 12, 1984 Completed By Frank Novachek Telephone (303) 785-2224 Nonth August, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (MWe-Net) 1 0.0 17 0.0 2 d.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0

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6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 ~ 0.0 9 0.0 ,__

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10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 l

13 0.0 29 0.0 ,

14 0.0 30 0.0 15 0.0 31 0.0 l

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'* Generator ~on line but no net generation. -

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. REFUELING INFORMATION I l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l 1 l 2. Scheduled date for next l 4th Refueling: l l refueling shutdown. I 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 cperation 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 l l If answer is no, has the reloadj 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

.I associated with the core reload l l l (Reference 10 CFR Section l l l l 50.59)? l l

. l l l l l If no such review has taken l 1985 l l place, when is it scheduled? I 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

chang s 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 H7GR fuel elements l l spent fuel storage pool. I b) 197 spent fuel elements l a

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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).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

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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 F Cdomndo l l

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

1 September 13, 1984 Fort St. Vrain linit #1 P-84352 Office of Inspection and Enforcement ATTN: Occument 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 August, 1934.

Sincerely,

/W J. W. Gahm Manager, Nuclear Production Enclosure cc: Mr. John T. Collins JWG/djm l

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