ML20095D739

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Revised Monthly Operating Rept for June 1984
ML20095D739
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/30/1984
From: Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20095D733 List:
References
125, NUDOCS 8408230459
Download: ML20095D739 (8)
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION

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MONTHLY OPERATIONS REPORT NO. 125 June, 1984 l

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

({J' No. 1, activities operated under the provisions of the. Nuclear Regulatory Commission Operating- License DPR-34. This report is for the month of June,1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE At the beginning of June,1984, the reactor was being operated at approximately 8% power, while primary and secondary coolant chemistry cleanup continued.

' On June 2, reactor power was reduced to less than 2% to allow for the repair of an hydraulic oil leak on HV-2224, and for leak checks on several other hydraulically operated valves.

Reactor power sas slowly increased, beginning June 3, as reactor oewpoint and feedvcater iron concentration levels would allow.

The turbine generator was synchronized on June 12, but tripped -

within one hour due to low main steam temperature. Main steam temperature was inadequate, due to reactor power being limited by Technical Specification requirements on moisture. A second attempt was made later in the day but resulted in another trip on low main steam temperature. During the short period of operation, the No. 5 turbine bearing exhibited a higher than '

() normal vibration.

The turbine generator was placed in service on June 13, at 2127 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.093235e-4 months <br />, at approximately 50MW.

Flushing of both high pressure feedwater heaters was completed and the heaters returned to normal service on June 14, 1984.

The turbine generator was removed from service on June 16, to perform overspeed tests.

Reactor power was increased above 30% on-June 21, and as high as 53% on June 22, when operation of the sudden pressure relay on the 4160/480V Transformer No. I caused a trip of the 480V A.C.

Essential Bus IA and subsequently, the 1A Helium Circulator due to a bearing water upset. This transient resulted in water ingress to the primary coolant via the 1A Helium Circulator.

Power.was reduced, and the circulator was recovered.

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. t Increasing moisture, problems with the helium purification

'- system, and other compounding conditions caused a reactor scram on high pressure on June 23, 1984, at 0028, following the 1A helium circulator upset. During the event, six of the thirty-seven control rod pairs failed to automatically insert upon actuation of the Plant Protective System (PPS) Scram Logic.

A powered insertion of the stuck rods was initiated, and all rod pairs were fully inserted by 0049, on June' 23. Although some rods failed to initially insert, cold shutoown conditions were achieved with the initial scram. Investigation into the problem is continuing. Nuclear Regulatory Commission approval will be necessary prior to reactor startup.

Due to higher than normal vibration, the 1A boiler feed pump internals have been removed and sent out for inspection / repair.

Weights are being installed in the main turbine generator to decrease vibration at tae'No. 5 bearing.

At present, the reactor remains shut down pending resolution of the control rod drive problem and Nuclear Regulatory Commission -

concurrence in starting up. -

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF- 10% OF THE ALLOWABLE ANNUAL VALUE l

None. '

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i 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL  !.

EXAMINATION None.

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4.0 MONTHL"Y OPERATING DATA REPORT f

Attached.

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- Iccue 2 i Ptge 1 e:f 1 OPERATING DATA REPORT DOCKET NO. 50-267 DATE Aunust 13. 1984 a COMPI.ETED BT Chuck Fuller TELEPHONE (303) 785-2224 OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain ,
2. Reporting Period: 840601 throuch 840630
3. Licensed Thermal Power (wt): 842
4. Nameplate Rating (Gross We): 342
5. Design Electrical Rating (Net we): 330
6. Nazimum Dependable Capacity (Gross We): 342
7. Maximum Dependable capacity (Net We): 330
8. If Changes Occur in capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Vhich Restricted, If Any (Net We): 280
10. Raasons for Restrictions, If Any: Per commitment to the NRC, lone term operation above 85% power is pending completion of the B-0 Startup Testing.

This Month Year to Date cumulative

11. Bours in Reporting Period 720 4,367 43,848 528.5 1,324.1 27,151.4 ,'
12. aumber of sours Reactor Vas Critical
13. Reactor Reserve Shutdown Hour. 0 0 0
14. sours cenerator On-Line 213.5 660.1 18,463.3
15. Unit Reserve Shutdown Hours 0 0 0
16. cross Thermal Energy cenerated (w n) 92,004.7 340,407.9 9,861,725.3 l
17. cross Electrical Energy Generated (WH) 17,732 95,144 3,248,594 l
18. Net Elaetrical Energy cenerated (w n) 12,734 73,998 2.945,525 l
19. Unit s'ervice Factor 29.7 15.1 42.1
20. Unit Availability Tactor 29.7 15.1 42.1
21. Unit Capacity Tactor (Using MDC Net) 5.4 5.1 20.4 l
22. Unit Capacity Factor (Using DER Net) 5.4 5.1 20.4 l
23. Unit Forced Outage Rate 51.7 26.3 39.1
24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each): 7-1-84 through 9-1-84, 1488 hours0.0172 days <br />0.413 hours <br />0.00246 weeks <br />5.66184e-4 months <br />, Control Rod Drive investigation; 10-19-84 through 11-10-84, 552 hours0.00639 days <br />0.153 hours <br />9.126984e-4 weeks <br />2.10036e-4 months <br />, surveillance testing. *
25. If Shut Down at End of Report Period, Estimated Date of Startup: 9-1-84
26. Units In Test Status (Prior to Con:mercial Operation): Forecast Achieved INITIAL CRITICALITT N/A N/A INITIAL ELECTRICITT N/A N/A co.WCIAL OPERATION N/A N/A u____ -_-

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  • - Attachment-3A a 2 i AVERAGE DAILY UNIT POWER LEVEL p g

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Docket No. 50-267 l

Unit Fort St. Vrain Date August 13, 1984 Completed By Chuck Fuller Telephone (303) 785-2224 Month June, 1984

  • DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MRe-Net) 1 0.0 17 69.7 2 '.0 0 18 72.0 3 0.0 19 72.8 4 0.0 20 70.5 5 0.0 21 94.7' l 6 0.0 22 91 3 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 l 13 0.0
  • 0.0 29 14 61.8 30 0.0 15 65.9 31 N/A l 16 _

51.5

  • Generator on line but no net generation.

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50-267

_un T unnE Fort St. Vrain

, ante August 13, 1984 Colet.ETED av Chuck Fuller REroRT Holm1 June, 1984 TEt.ErnonE (303) 785-2224: .

HE1110D OF SilUTTTIOC DOWII SYSTEM C00FOIIElff 11 0 DATE TYPE DUltATION REASON REACTOR LER f CODE (DDE CAUSE AND CORRECTIVE ACT10ll 10 PREVENT RECURRENCE 84- 840601 S 277.9 H 4 N/A ZZZ ZZZZZZ Primary. coolant cleanup. Reactor at 002 low power.

84- 840612 F 5.5 H 4 N/A SB TT Turbine trip due to low main steam 003 temperature. Reactor remained critical.

84- 840612 F 25.0 H 4 N/A

84- 840616 F 3.9 B 4 N/A JJ ST Turbine generator overspeed test.

005 Reactor remained critical.

84- 840622 F 194.2 H 3 50-267/84-008 JC PT 1A helium circulator trip caused a 006 water ingress to the primary coolant.

The turbine generator was tripped and a power decrease was in progress when a reactor pressure high scram occurred.

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REFUELING-INFORMATION' s

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.[ 1. Name of Facility i Fort St. Vrain Unit No.1 ~l l l l' (l 2. . Scheduled date for'next .l 4th Refueling: l.

l refueling' shutdown. ~l February 1,-1986 l.

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. . .I . 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 operation thereafter require a~l l l technical specification change l l l or other license amendment? I 'l.

I - 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 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)? l l l l l

-l If no such review has taken l 1985 l l place, when is it scheduled? l l l l l l S. 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 j l 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 1482 HTGR-fuel elements l

[ spent fuel storage pool. I 251 spent HTGR fuel elements 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. I l 1 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

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..t 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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