ML20043G140

Monthly Operating Rept for May 1990 for Calhoun Station, Unit 1.W/900614 Ltr

ML20043G140
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1990
From:	Gates W, Stice D OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0514, LIC-90-514, NUDOCS 9006190113
Download: ML20043G140 (7)

Text

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Omaha Public Power District 1623 Harneu Omaha. Netnaska 68l02 2247 402/536 4000 June 14, 1990 i IJC-90-0514  ;

U. S. Nuclear Regulatory Comission  !

Attn: W w nt Control Desk l

Mail Station P1-137 Washington, DC 20555

References:

Docket No. 50-285 Gentlemen: ,

SrJBJECI': May Monthly Operating Report (POR)

Please fird enclosed one copy of the May 1990 Monthly Operatirg Report for the -

Fort Calhoun Station Unit No. 1 as required by Technical Specification Section '

5.9.1.

If you should have any goestions, please contact me, Sincerely, M

W. G. Gates Division Mana er '

Nuclear Operations EG/sel

- c: leBoeuf, Lamb, leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV P. H. Harrell, NRC Senior Resident Inspector D. K. Sentell - Otznbustion Engineering R. J. Simon - ikustinghouse '

i Office of Management & PIugram Analysis (2)

Nuclear Safety Analysis center i INIO Records Center American Nuclear Insurers 9006190113 900531 PDR ADOCK 05000285 R PDC 4% St?4 Employment wito Equai Opportunity MaleTemale  ! l ,l ,

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l AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50-285 UNIT Fort Calhoun Statio~

DATE June 14, 1990 COMPLETED BY 6. L. Stice TELEPHONE (402)636-2474 MONTH May 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 _

0 17 0 2 0 18 0 3 0 19 0 1 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 _

24 0 9 0 25 0 10 0 26 0 11 0 27 0 _

12 0 28 0 13 0 29 16 14 0 30 100 15 0 31 79 16 0 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt, i

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. OPERATING DATA REPORT 4 DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE June 14, 1990 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474 OPERATING STATUS

1. Unit Name: Fort Calhoun Station

~ Notes

2. Reporting Period: May 1990 ,

3. Licensed Thermal Power (MWt): 1500

4. NameplateRating(GrossMWe): 502

5. Design Electrical Rating (Net MWe): 478

6. Maximun Dependable Capacity (Gross MWe): 502

7. Maximum Dependable Capacity (Net MWe): 478

8. If changes occur in Capacity Ratings (Item Numbers 3 through 7) Since Last Report, Give Reasons:

N/A

9. PowerLeveltoWhichRestricted,IfAny(NetMWe): N/A

10. Reasons for Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 3,623.0 146,233.0 $

12. Number of Hours Reactor was Critical 149.5 1,291.6- 112,457.9 i

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 56.3 1,186.9- 111,192.3 ,

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 21,625.1 1,697,525.8 145,312,637.0

17. GrossElectricalEnergyGenerated(MWH) 5,864.0 552,730.0_ 47,762,838.2

18. Net Electrical Energy Generated (MWH) 4,669.6 526,575.8 45,594,128.6

19. Unit Service Factor 7.6 32.7 76.0

20. Unit Availability Factor 7.6 32.7 76.0 1

21. UnitCapacityFactor(UsingMDCNet) 1.3

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30.4 67.7

22. Unit Capacity Factor (Using DER Net) 1.3 30.4 66.1

23. Unit Forced Outage Rate 0.0 0.0 2.9

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): f Maintenance shutdown tentatively scheduled for July,1990 with estimated duration of 3 days to balance generator.

25. If Shut Down at End of Report Period, Estimated Date of Startup: N/A l 26.. Units In Test Status (Prior to Commercial Operation): Forcast Achieved l INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION i l

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DOCKET NO. 50-285 UNIT NME Fort Calhoun Station DATE June 14. 1990 .

UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY D. L. Stice TELEPHONE (402) 636-2474 REPORT MONTH May 1990 5 ~

E 52 E 3 Fj uce,.e.

gg g ca.ee a ceneen.

No. Date , "

. 5 )Eg Event g Eo Action to

? E- g e yh'j Report s u o hw w 90-01 900217 5 2436.1 C 1 N/A XX XXXXXX On February 17,1990, the 12th Fort

! Calhoun Station Refueling Outage commenced. The generator was put back on-line May 29, 1990.

I 1 2 3 4 F-Forced Reasort Method- Exhtit G - histructione S-Schedded A-Equipment Fagure (Explaint t-Manuel for Properation of Data B-Meintenance or Test 2-Manuel Scram Entry Sheets for Uconese C-Refue3no 3-Automatic Scram Event Report S.ER) FRe SUEG-01815 D-Reedstory Restric' ion 4N WExplektl E-Operator Training a Ucense Examinetton 5 F-A4ninistative Exhtet 1 - Some Source G-Operational Error H-Other (Explain)

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3 Refueling Infonnation

• Fort Calhoun - Unit No.1  ;

Report for the Inanth endirg May 1990 ,  ;

1.- Scheduled date for next refueling shutdown. SeDtanber 1991 ,_

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2. Scheduled date for restart following refueling. November 1991 '

3. = Will refueling or resunption of cperaticra thereafter require a technical specification change or other license amendment? Yes

a. If answer is yes, what, in general, will these be?

Incorporate specific requirements resulting frcan reload safety analysis. ,

b. If answer is no, has the relaod fuel design and core configuration been reviewed by your Plant safety review cannittee to determine whether any unreviewed safety questions are associated with the core reload. N/A

c. If no such review has taken place, when is it scheduled? N/A

4. Scheduled date(s) for subnitting puM licensing action and support informhtion. June 1991

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unrevie nt design or

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performance analysis methods, significant >

changes in fuel design, new operating procedurec. New fuel supplier New IDCA Analysis

'6. 'Ihe number of fuel ancamblies: a) in the ooIB 133 Assemblies b) in the spent fuel pool 477 Assemblies c) spent fuel pool storage ,

capacity 729 Ar,semblles d) planned spent fuel pool Planned to be increased storage capacity with higher density spent fuel racks.

7.- 'Ihe projected date of' the last refueling that can be discharged to the spent fuel pool a==nnMg the present licensed capacity. 1994*

• Capability of full core offload of 133 assemblies lost.

Prepared by 4 Mf AM- Date June 11. 1990

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• • 'I

. , - CHMR IUBLIC POWER DISIR1CT )

Fort Calhoun Station Unit No. 1 I

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May 1990 )

M:rithly Operatirg Report I. OPERATIONS SO9%RY Fort Calhoun Station canpleted its twelfth refueling and maintenance l outage. Emergency safety feature testing and other surveillance testiry required durity refueling shutdown was ocmpleted. '1he annual inspection was otmpleted for Emergency Diesel Generator DG-2.

Plant heatup from the refueling shutdown was started on May 19, 1990. 'l Minor Reactor Coolant System (RCS) leaks detected during the Hydrostatic l Test were repaired and the RCS heatup to hot shutdown was ocupleted May 22, 1 1990. 'Ihe reactor was made critical May 25 and low Power Physics Testing j was ocmpleted May 27. 'Ibe generator was placed on-line May 29 at 3:39 P.M. ]

Power was brought up to 30% to bring Steam Cenerator Secondary Chemistry i

. into specifications, and then held at 30% for a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> boric acid soak. A 1 bearing on the main generator had above normal vibration levels which are being monitored through the power increase.

'Ibe following NRC inspections took place in May:

IR90-26 Residents' Monthly Inspection (04/15/90 to 05/14/90)

IR90-30 Residents' Mcrithly Inspection (from 05/15/90 to present)

'Ihe following IERs were subnitted: Date Submitted 90-801 Inadequate Ctmpensatory Measures May 9, 1990 90-11 Inadvertent Actuation of Pressurizer Pressuru May 10, 1990 low Signal 4

90-12 Inadvertent Diesel Generator Start May 25, 1990 90-13 Alignment Pin Damage While Moving Reactor Head. May 24, 1990 90-14 Potential Ctmponent Cooling Water / Containment May 29, 1990 Isolation Failure A. SAFEIY VALVES OR FORV CHALIENGES OR FAIIURES WHICH OOCURRED None B. RESULTS OF IEAK RATE 'IESTS

'Ibe results of the Reactor Coolant Systan leak rate test for May,1990 show the effects of the 1990 Maintenance ard Refueling Outage.

Although the " total" ard unknown" leak rates are inaccurate due to the additions of water ard boric acid during the tests, the overall trend observed durity these tests irdicates that the maintenance perfonned during the outage was successful. )bst of the "known" leakage to the Reactor Coolant Drain Tank (RCDr) last cycle came frtra the Pressurizer Spray Valve packing leakoffs. Both Pressurizer Spray Valves were repacked and now their leakoff lines are cool and the "known" leakage to the RCDP has been reduced frun about 0.5 gpu to about 0.05 gun. j

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e. . 3 c<

Monthly Operatirg Report May 1990 ,

Page h o We -4== leak rate for the month was recorded on May 22, 1990, with a total leak rate of 0.290 gpn and an unknown leak rate of -0.356 gpn. l

'Iho minimmi leak rate for the month was recorded on May 29, 1990 with ,

total leak rate of -0.403 gpn and an unknown. leak rate of -0.455 gpn. l h e negative leak rates are due to the inaccuracies induced into the  :

tests. %ese inaccuracies are caused by the diluticn of the Reactor Coolant System as required to achieve criticality and to overcome the power coefficient and fission product poisoning reactivity effects.

• C. OIANGES, TESIS AND EXPERIMENTS REQUIRING NUCIEAR REUUIATORY CDMISSION AUIHORIZATION IURSUANT TO 10CFR50.59 Aliierdiscut No. Descriotion 1 No. 130 This hiinsrdisnt modifies Technical Specification 2.12, Control Room Systems. Se amerdment l conservatively lowers the maxima limit for control '

rocan air tenperature (frun 120*F to 105'F) upon which OPPD is required to take action. This change <

was ruma=ayy in order to more accurately direct the application of the Technical Specification to the equipnent it was originally intended to address.

No. 131 This amentnent nodifies the Technical Specifications for the Chemical and Valve Control System such that the boric acid concentration would be lowered, and heat tracing of the circuits would no longer be required. The revised specifications also more clearly define: (1) the volume and concentration of boric acid to be maintained in the Boric Acid Storage Tanks (BASTS), and (2) the f1cw paths from the BASTS to the reactor coolant system durirg various modes of plant operation.

II. MAINTENANCE (Significant Safety Related)

See Section I. Operations Sunanary Gary R. Peterson Manager-Fort Calhoun Station l

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