ML20086L573

Monthly Operating Rept for Nov 1991 for Fort Calhoun Station Unit 1

ML20086L573
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1991
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-91-326R, NUDOCS 9112170001
Download: ML20086L573 (8)

Text

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1 Omaha Public Power District 444 South 16th Street Mall i Omaha. Net >raska 68102-2247 402/636-2000 LIC 91-326R December 13, 1991 V. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20559

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

November Monthly Operating Report (NOR)

Enclused is the November 1991 MOR for Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification Section 5.9.1.

If you should have any questions, please contact me.

Sincerely, 44IME p V W. G. Gates Division Manager Nuclear Operations WGC/sel Enclosures c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident inspector D. K. Sentell, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)

INPO Records Center American Nuclear insurers

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AVERAGE DAILY UNIT POWER [fVEL DOCKEI NO. 50-?85

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UNIT Iort Calhoun 5IatTii5 DATE becemfieF9, 1991..

COMPLETED BY R. L. Edwards TELEPHONE T402)TBUN51 MONTH November 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Het) (MWe-Net) 1 487 17 487 2 487 18 487 3 487 19 486 4 487 20 486 _

5 487 _

21 485 _

6 487 22 486 7 487 23 486 _,

8 ,

487 _

24 486 9 487 25 486 e 10 487 26 486 Il __

488 27 486 ..

12 488 28 487 13 488 29 4WI 14 488_ _ 30 487 15 487 16 487 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.

., OPERATING DATA REPORT ,

DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE December 9,199T~~~

COPLETED BY h. L. Edwards '

TELEPHONE I452TE W 2451 OPERAT!hG STATUS

1. Unit Name Fort Calhoun Station ~

Notes

2. Reporting Period: November f791

3. Licensed Thermal Power (MWt): 1500 _

4. NameplateRating(GrossMWe):_ .

502

5. DesignElectricalRating(Net'HWe): 47 8

6. MaximumDependableCapacity(GrossMWe): 502 ~

7. ~T76~

8. MaximumDependableCapacit'y(NetMWe)(:

If changes occur in Capacity Ratings ItemNumbers3through7)SinceLastReport, Give Reasons: '.

.N/A-

_ _.2

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 ~

720.0 ~

8,016.0 159,386.0

12. Number of Hours Reactor was-Critical 720.0~ 7,286 T 124 TiTC T

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5~

14.- Hours Generator On-Line 720.0 7,2DI T 1222 633.1

15. Unit Reserve Shutdown Hours 0.0~ 0.0 ~

0.6~

16. GrossThermalEnergyGenerated(MWH) 1,076,325.2 9,228,684.4~ 160,5121173.7

'17. 366,755 6~ 3l047,4E6 U~ ~52,797,503.2 Gross Electrical

18. NetElectricalEnergyGenerated(MWH) Encrgy Generated (MhH) ~~3E0,526.02,887,287.2 ,, 50,1372,063.5. r

19. Unit Service Factor 100.0 ~

89.9 76.9 ,

20. Unit Availability factor 10iT.T 89.9 ~~~

76.9

21. Unit.CapacityFactor(UsingMDCNet) 10f.8 ~~~

75.1 '

68.4

22. Unit Capacity Factor (Using DTR Net) ~ 101.8 75.4 66.9 .,

23. Unit Forced Outage Rate 0.0 f6.1 3.9

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Cach):

Refueling outage scheduled to begin February 1, 1992 and last approximately three months.

25. TT Shut Down at End of Report Period, Estimated Date of Startup: N/A .

26. Units In Test Status (Prior to Commercial Operation): Forcast Achieved ,

l' INITIAL CRITICALITY '

L. INITIAL ELECTRICITY N/A-COMMERCIAL OPERATION t

y >

. Refueling Inforcation

, fort Calhoun Unit No. 1 Report for the month ending _Novetnber 191L_._,

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1. Scheduled date for next refueling thutdown. ftbruar_Y-- l o 1992  ;

2. Scheduled date for restart following refueling.  ?*1L2L_HJ2_. .

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

a. If answer is yes, what, in general, will <

tnese be?

Incorporate specific requirements resulting from reload safety analysis,

b. If answer is no, has the reload fuel design and 1 core configuration been reviewed by your Plant Safety Review Committee 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 submitting proposed licensing action and support information. hy. ember 1991

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

performance analysis methods, significant changes in fuel design, new operating procedures. New fuel supplier hw_l&CA Analysis

6. The number of fuel assemblies: a) in the core 133 Assembliet b) in the spent fuel pool 477 auemblies c) spent fuel poel storage capacity 729 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density spent fuel racks.

7. The arojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present licensed capacity. Djt1 *

• Capability of full core offload of 133 assemblies lost. Roracking to be performed between the.1993 and 1995 Refueling Outages.

Prepared by T C .3d Date_ (2 + 4 I

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DOCKET NO. 50-285 __

UNIT NAME Fort Calhoun St.; ion DATE Deceeber 10. 1991 UNIT SHUTDOWNS AND POWER REDUCTIONS COMPLETED BY M. L. Edwards TELEPHONE (4021 636-2451 -

REPORT MONTH NOVEMBER 1991 I Cause & Corrective No. Date I Type Duration Reason Method of Ilxnw System Ce*

Gwle Code Actam to (Hours) (2) Shuttmg Event (1) 4 Prevent Recurre:sce Down Report # (4)

Reactor (3) t There were no umt shoulowns or ignificant a =---;in m durmg November 1991.

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i 3 4 1 2 Exhibit G - Instructxms for Preparation of Data Entry Sheets Reasore Method.

F-Forced for Licenze Event Report (LER) File (NUREG4161)

A-Equipment Failure (Explain) 1-Manual S-Scheduled B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Other (Exp;ain)

E-Operator Training & License Enmmation 5

F-A<iministrative Exbbit I - Same Surce G-Operatonal Error H-Other (Explain)

(9/77)

l I OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 November 1991 Monthly Operating Report

1. OPERATIONS

SUMMARY

Fort Calhoun Station (FCS) operated at a nominal 100% power throughout the month of November 1991. Early in November, the 345 KV electrical grid system experienced numerous disturbances due to the winter storm and associated icing that began on October 31, 1991. One of the disturbances on the turbine generator was so severe that a turbine plant cooling water pump tripped.

On November 6, 1991, the overhaul of main feedwater pump FW-4C was completed. Upon subsequent starting of the pump, the stainless steel flexible tube to the suction relief valve failed resulting in a high pressure steam leak. The pump was isolated by Operations personnel and allowed to cool. Later that week, replacement of the flexible tube allowed the pump to be put into service.

A four hour report was made to the NRC on November 6, 1991 due to an inadvertent actuation d Ventilation Isolation Actuation Signal (VIAS).

This occurred when an electrical maintenance worker pulled the incorrect fuse block during the performance of a tagging clearance. The report was made pursuant to 10 CFR 50.72(b)(2) because of the inadvertent actuation of an Engineered Safety Feature (VIAS).

A one hour report was made to the HRC pursuant to 10 CFR 50.72(b)(1) on November 14, 1991 because two support hangers on the Safety injection system were determined to be outside the seismic design criteria of the FCS USAR Appendix F. The installed hangers have a safety margin of 2.4 on the anchor bolts while the USAR Appendix F criteria requires a margin of 3.0.

The hangers are still considered operable based upon interim operability criteria allowing hangers with a safety margin of 2.0 or above on the anchor bolts to remain operable.

On November 19, 1991 the NRC notified the Training Department that all candidates (7 Reactor Operators and 7 Senior Reactor Operators) passed the initial licensed operator examination.

Due to severe winter weather on November 30, 1991, two unexpected fast transfers of vital 4160 volt buses IA3 and 1A4 from 161XV (off-site power source) to 345 KV (station power source) occurred. The first transfer occurrei as a result of a voltage fluctuation on the electrical grid system due to the loss of a 69 KV line which runs between fort Calhoun and Blair, Nebraska. The electrical distribution system was returned to normal alignment within approximately 10 minutes following confirmation from System Operations that 161 KV was available. The second unexpected fast transfer occurred due to failure of an insulator. After repairs were completed on the 161 KV line, the electrical distribution system was returned to its normal alignment. In both instances, immediate notification of the loss of 161 KV was made to the NRC.

The following NRC inspection took place during the month of November 1991:

IR 91-23 Routine Insp W lon I

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Monthly 0porating Report LIC 91-326R Page 2 The following LERs were submitted during riovember 1991:

Lf13L Descriotion 91-21 Inadvertent Containment Isolation Actuation Signal 91-22 Nuclear instrumentation Outside Design Basis (RG 1.97) 91-23 Failure to Meet Technical Specification Regarding Core Power Distribution Verification 1

91-10, R1 HELB Issue Related tt '1xiliary Steam in Room 57 A. SAFETY VALVES OR PORY CHALLENGES OR FAILURES WHICH OCCURRED None 1

3. RESULTS OF LEAK RATE TESTS l The total reactor coolant system (RCS) leakrate for November 1991 averaged approximately 0.35 gpm. The known leakrate to the reactor coolant drain tank (RCDT) increased to an average of 0.40 gpm. The known leakrate was greater than tha total leakrate because water downstream of the RCDT was leakint ' Jack into the dCDT through leaky check valves. As a result of th: larger known leskrate than total leakrate, negative unknown leakrate values were obtained for most of November 1991.

To minimize the effect of the check valve eakage on the RCS leakrate ,

value, the containment isolation valves fram the RCDT to the waste holdup tanks are now kept closed except when pumping the contents of the RCDT to the waste holdup tanks. This change was implemented on November 21, 1991 and has since resulted in the known leakrate falling to about 0.25 gpm with the unknown leakrate averaging less than 0.1 gpm. The leaky check valves are to be inspected and repaired during the 1992 refueling outage.

C. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT 10 10 CFR 50.59 AMENDMENT NO. DESCRIPTION 139 Adopted the guidance of Regulatory Guide 1.35 Rev.

3 for the surveillance of the containment tendons, i

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,- Monthly Operating Report  !

LIC 91 326R '

Page 3 D. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF NOVEMBER 1991:

Completed replacement of the demineralized water / rust inhibitor coolant from the jacket water system on both Emergency Diesel Generators with an antifreeze solution in preparation for cold weather.

During surveillance testing, a low flow condition was discovered on hydrogen analyzer pum) VA 818. The pump was found to be within s)ccifications, but tie flow rate was found out of tolerance due to t1e pump suction valve not opening fully. The valve was repaired and the surveillance test was performed to verify proper flow.

.