Text

Monthly Operating Rept for Jan 1982
	ML20041E407
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/08/1982
From:	Mcbride L; PUBLIC SERVICE CO. OF COLORADO
To:	;
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ML20041E189	List: ML20041E188; ML20041E407;
References
	NUDOCS 8203100478
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 97 January, 1982 l

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8203100478 820304 PDR ADOCK 05000267 R

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1 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 January, 1982.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Sr mary The loop split modifications continued through the entire month of January, with approximately 75% of the work complete at the beginning of the month, and at months end, approximately 93% was completed Reactor core cooling during this period was being i

maintained primarily by the components available in Loop 1, as Loop 2 was shutdown to replace the "0" rings in the hydraulic s3 stem supplying the oil to the operators of all major primary and secondary coolant valves in Loop 2.

There were several scheduled interruptions to core cooling, limited to less than 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months each, to allow tie-ins of some of the more critical system components, and also to aid in the cleanup of the primary coolant helium.

Testing was conducted on Loop 1 steam water cump system to verify that this system trip would not reset without operator action.

This test must also be performed on Loop 2 prior to startup. Numerous functional tests were also performed on the new equipment installed in the helium circulator auxiliary system.

This testing program will continue during the initial return-to-full power to verify all parameters meet their intended design specifications.

As the end of the month approached, plant system modifications were nearing completion.

System 21 circulators in Loop 1 were operating on buffer helium circulated through one of the new dryers, with in-service testing indicating those areas needing adjustments. The main turbine generator alignment problems were solved and workers were re-assembling the unit.

Several jobs that Public Service Company's Maintenance Department had been working in conjunction with the loop split outage are nearing completion.

Barring any unexpected future complications, the plant should be ready for Nuclear Regulatory Commission administered licensed operator criticality tests near mid-February and subsequent rise-to-power.

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' 2.1 Operations The loop split modifications were of primary concern during the month of January with approximately 75% of the work completed at the beginning of the month and 980 completed by months end.

Public Service Company's Maintenance Department also completed jobs that have been waiting for an outage of this extent to perform.

Some of the more important jobs were:

1) Repair of leakage on PV-2352 and M-2308 in the System 23 regeneration pit.

2)

Installation of 1A hydrogen getter.

3), Repair of 1A and IB condenser pumps.

4) Repair of circulating water pump suction and discharge valves.

5) Overhaul of alternate cooling method diesel generator engine.

6) Replacement of 1A Diesel Generator Room cooling coil.

7) Repaired crack in bell housing of IB diesel generator.

8) Replacement of TCV-5207 and TCV-5208.

Reactor core cooling was maintained during this period primarily by Loop 1 as Loop 2 was shutdown to replace "0" rings in the System 91 hydraulic lines.

Several scheduled interruptions to core cooling we-e made to allow tie-ins of some of the locp split modifications. The longest of these interruptions was from 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months on January 20 to 1417 hours0.0164 days 0.394 hours 0.00234 weeks 5.391685e-4 months en January 22.

Testing on Loop 1 steam water dump syste'm to determine that a system trip would not reset without operation action was successfully completed.

Loop 2 testing is scheduled to be done as soon as the equipment is available. Other testing, including the Functional Tests and cold checkouts of the newly installed equipment, was being carried out cally by the Results and Electrical Departments.

Toward months end, more systems were secoming operable.

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Loop 1 circulators were operating with buffer helium supplied from the new Loop 2 helium dryer. The Operations and Results Departments were busy observing and making adjustments to the new control systems to obtain better system response. Construction work was approximately 98%

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complete,. the remainder consisting mostly of pipe support and building structural changes.

The main turbine generator alignment problems had been corrected, and re-assembly of the unit was well on its way with a target date for completion the first week in February.

Primary coolant pressure was increased to 100 psi on January 31 and will be increased to full inventory when the B-2-3 steam generator penetration work is complete sometime the first week of February. After that, several license candidates are required to perform Nuclear Regulatory Commission administered reactor starts. After a period of low power primary coolant and water chemistry cleanup operation, the plant should be ready for power operation.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS 6F 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached i

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ISP-3 Att achan t-2

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CPERAT!UC OAT!. W OFT 30CIET 50.

50-267

Art 820208 cc.>LI:23 3T L. M. McBride v

TELErs0NE 785-2224 OPDATT'fC STATUS i :sorzs 1.

Unic Nees:

Fort St. Vrain 2.

seyrcing period:

820101 through 820131

'. Licensed thermal Power (Nt):

842 4.

Nameplace Rating (cross We):

342 3.

Oesign Electrical Rati=g (Net se):

330 6.

Mart== 3ependable Capacity (Gross We):

342 7.

Maximus Dependable capacity (Net se):

330

.$. If Changee Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, cive Reasons:

Nana 9.

Power Level To nich leetricted. If Any (Net We): 23J

10. amasons for Restrictions. If Any:

NRC restriction of 70% pending resolution of 1

temoerature fluctuations.

This ! bath Year to Date Cumlative

11. Hours in Reporting Period 744.0 744,0 22,705 1:. Number of sours Reactor was critical 0.0 0.0 14,578.4

12. Reactor Reserve Shutdown sours 0.0 0.0 0.0 la. Hours cenerator on-Line 0.0 0.0 9.908.3

13. Cnic Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Emergy Generated (51) 0.0 0.0 4.933.944.8

17. Cross Electrical Inergy cenerated (Wu) 0.0 0.0 1.691.356

13. Net Electrical is.rty Generated (51)

-1 o50

-1.950 1.552.309

19. Unit Service Factor n_n O.O

&1.6

20. Unit Availability Factor 0.0 0.0 43.6

1. :nic capacity ractor (catng Mac Net) 0.0 0.0 20.7 2:. Unit capacity Tactor (Csing DER Net) 0.0 0.0 20.7

3. Unic Forced outage zate 0.0 0.0 34.0 l

26.

Shutdowns Scheduled over Next 6 tenths (Type, sate, and Duration of Each): Maintenance /

l modif4cneton shutdown 2-1-82 throuch 2-28-82.

23.

If Shut Down at End of 2eport Period. Escinated Oate of Startup March 1.

1982 l

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Onits In Test Status (Prior to comercial Operation):

Torecast Achieved l

I :AL cal : CAL::T N/A N/A l

I::t::AL ELIC 2:c::T N/A N/A c:mHExc:AL CPERATION N/A N/A l

TEP-3 A Issa 2 AVERAGE DAILY INIT POWER LEVEL Page 1 of 1 Docket No.

50-267 Unit Fort St. Vrain Data R20208 L. M. McBride Completed By 785-2224 Telephone M) nth January, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL..

(MWe-Net).

(MWe-Ne t) 1 0.0 17 0.0 2

0.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 3

0.0 21 0.0 6

0.0 22 nn 7

0.0 23 0.0 S

0.0 24 0.0 9

0.0 25 0.0 10 n.n 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

Generator on line but no net generation.

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' tame of ?ard ' d-r.

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Scheduisd data h r =az: :staaling shu:down.

Oc cber 1. 1983 3.

Scheduled da a for :ssear:

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specifica:ica change or other license = -r!" ant?

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1an been :sriswad by ycur Plan:

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succor d=g inf:r=a:1cu.

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e.g., new or diff erenc faal de-sign or supplier, nrsviswed design or perfor..a=ca analysis i

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size of a=7 i=censse i= lica= sed

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raquas:sd or is pla==ed, i=

f m-*er of fual asse=clies.

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REFUELING I:TFORMAT'ON (COTTINUED) 9.

The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

licensed caeaciev.

The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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ML20041E407

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