ML19351E930

Monthly Operating Rept for Nov 1980

ML19351E930
Person / Time
Site:	Fort Calhoun
Issue date:	12/09/1980
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19351E927	List: ML19351E926 ML19351E930
References
NUDOCS 8012190542
Download: ML19351E930 (9)

Text

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AVER AGE DAILY UNIT POWER LEVEL O

50-285 DOCKET NO.

UNIT Fort Calhoun #1 DATE December 9, 1980 COMPLETED BY T. L. Patterson TELEPHONE (402)536-4413 November, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe Net) 1 334.4 37 389.6 333.6 389.4 2

18 3

339.0 389.5 39 4

343.9 20 389.9 5

345.1 384.3 21 6

346.3 22 360.8 7a 348.6 23 358.4 8

348.5 357.1 24 l

9 347.7 25 357.8 10 348.2 357.3 26 11 348.6 357.6 27 348.8 357.6 32 28 337.1 358.1 13 2,

249.5 357.5 34 3a 376.5 15 3,

16 386.6 INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day in the reporting month. Compute io the nearest whole megawatt.

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801219 05'/4L

OPERATING DATA REPORT DOCKET NO. 50-285 DATE December 9, 1980 COSIPLETED BY T. L. Patterson TELEPitONE 14021536-4413 OPERATING STATUS Fort Calhoun Station Unit No.1 Notu

1. Unit Name:

2. Reporting Period:

November, 1980 Reactor power held at 75%

3. Licensed Thermal Power (MWt):

1500 throughout the month to

4. Nameplate Rating (Gross MWe):

513 conserve fuel.

5. Design Electris! Rating (Net MWe):

490 513

6. Masimum Dependable Capacity (Gross MWe):

490

7. Mnimum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Gise Reasons:

N/A N/A

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9. Power Lese!To Which Restricted,1f A

'et MWe):

10. Reasons For Restrictions. lf Any:

This Month Yr.-to Date Cumulative

11. Ilours in Reporting Period 720.0 8,040.0 62,977.0

12. Number Of ' fours Reactor Was Critical 720.0 4.632.7 49,03 Q

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On Line 716.1 4.564.8 48.016.9

15. Unit Reserse Shutdown flours 0.0 0.0

'0.0

16. Gross Thermal Energy Generated (MWil) 809.219.3 5.645.774.4 58,880,803.7_

17. Gross Electrical Energy Generated (MWII) 271 J3J11._,

1.846.580.0

_19.506.809.6

18. Net Electrical Energy Generated (MWil) 255,533.3 1,745,435.4 18,432,955.2

19. Unit Service Factor 99.5 56.8 76.2

20. Unit Availability Factor 99.5 56.8 76.2 72.4 46.9 64.3

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 72.4 46.9 63.9

23. Unit Forced Outage Rate 0,5 0.4 4.1

24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Each):

None l

25. If Shut Down At End Gf Report Period. Estimated Date of Startup:

N/A

26. Units In Test Status aPrior eo Commercial Operation):

Forecast Achiesed.

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INill A L CRITICALITY INITIA L ELECT RICITY COT!\\1ERCIAL OPER ATION l

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(9/77)

t 50-285

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME.,F _rt Calhou'n #1 J2 DATE.pecember 9, T980 COMPLETED BY T L _ Pattorson REPORT MONTil November, 1980

~IELEPilONE (402)S36-4413 l

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.E' Licensee P,

be Cause & Corrective 1

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Date g

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,g g 5 Event u?

!'3 Action to

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Report a nU

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Prevent Recurrente e;

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6 80-04 801114 F

3.9 A

4 N/A CB VALVEX Generator taken off-line to repair l

packing leak on, reactor coolant sample line root valve RC-138.

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2 3

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F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 1

B Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee i

C. Refueling 3 Automatic Scram.

Event Report (LER) File INUREG-l-

D-Regulatory Restriction 4 Other (Explain) 0161) i E-Operator Training & License Examination i

F-Administratise 5

1 G-Operational Error (Explain)

Eshibit I - Same Source (9/77)

II-Ot her (Explain)

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Refueling Infonration l' ort Calhoun - Unit No.1 Pcport for the mnth ending November 1980 1.

Scheduled date for next refueling shutdown.

September 15, 1981 November 15, 1981 2.

Scheduled date for restart folloaing refueling.

3.

Will refueling or restnprion of operation thereaf ter require a technical specification change or other No license a::end: Tent?

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

these be?

b.

If ars.eer is no, has the reload fuel design and core configuration been reviced by your Plant Safety Review Cormtittee to deter-mine whether any unrevicwed safety questions NO are associated with the core reload.

If no such review has taken place, when is c.

Septeraber 1,1981 it scheduled?

4.

Scheduled date(s) for submitting proposed licensing action and support infonration.

5.

Imortant licensing consideratic,ns associated with refueling, e.g., nca or different fuel design or supplier, unreviewed design cr perfomance analysis mthods, significant changes in fuel design, nca operating procedures.

133 assemblies 6.

The ntnber of fuel assemblies: a) in the core b) in the spent fuel pool 197 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483 7.

The projected date of the last refueling that can be discharged to the spent fuel pool asstating the present 1985 licensed capacity.

W Inte December 1, 1980 Prepared by y

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OAHA PU3LIC POWER DISTRICT Fort Calhoun Station Unit No. 1 November 1930 Monthly Operations Report I.

OPERATICUS SI20'aRY Fort Calhoun operated at essentially 755 pcVer during the month of Nove=ber. The pcVer history during the =cnth of Nove=ber was as follevs:

1.

November 1 - 12, Approximately 655.

2.

November 13, Approximately a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> outage to co=plete repairs on an instr :ent root valve in ecntainment.

3 Nove=ber 15 - 21, Increase in reacter power to approxi-

=ately 825.

h.

Nove=ter 19 - 30, Decrease and =aintain approximately 75% power.

Preparation cf the candidates for a Reactor Operators license tests continued during the senth of Nove=ber.

The Supervisor-Operations attended the A=erican Nuclear Society Semi-Annual meeting in Washingten, D.C. on November 16 thru 19 Operaticnal and Surveillance testing continued as scheduled.

A.

PERFO? MICE CHAPACTERISTICS LER Number Deficiency LER-025 Dur.ng power operation while co=pleting repairs on "C" charging pump, "A" charging pump become inoperable due to a veld leak. Technical Speci-fications 2.2 was implemented and maintenance was initiated en "A" charging pump i= ediately.

Technical Specificaticns allow this =cde of operation for 2h hours. The veld was repaired and the pu=p returned to service the same day.

LER-026 During testing of the matrix logic for the reactor protective system, it was discovered that the AB-1 = atrix relay failed to trip the clutch power supplies. The failure resulted in only slight dedradation of the systes since five of the six logic units were properly working.

The failure resulted in the loss of'one of the four trip relays in one of the six assemblies.

Fanthly Operstions Report November 1930 Page Two A.

PERFCF3XICE CHARACTERISTICS (Ccntinued)

LER *!u-ber Deficiency LER-027 During the perfornance of Surveillance Test ST-ESF-5, Section F.1 (the monthly AC sequencer ti=er test ), ti=er F'4-6 ( Aur. FW Pump) on sequencer S1-2 failed to time out within the prescrihed limit. During the tine of the failure, the DC sequencer circuitry which activates F'4-6 as well as the AC and DC sequencer circuitry actuating the redundant Aux. Feedvater Punp (F'4-10) vere found to be operating as designed.

LER-028 At 0850 during the perfor=ance of ST-ESF-6, F.2, diesel generator DG-1 was started and run to operating speed. However, the bu::er which tests for DG-1 " ready-to-load" within 10 seconds failed to sound within the prescribed time limit. Upon subsequent retesting, the DG-1 diesel generater failed to start upon actuation of Channel A full speed test switch. As a result of DG-1 failure to start, the redundant diesel generator was satisfactorily tested for operability and it was verified that there were no associated incperable safeguards equipment.

3.

CFEIGES IN OPERATING METHODS IIone C.

RESULTS OF SURVEILIX;CE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Sectica 3 0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a sunnary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operatiens Incident

' cncy OI-1050 ST-ESF-6 DG-1 failed to start upon actuation of Channel A full speed test switch.

OI-1012 ST-ISI-SI-l On-The-Spot change to reflect recorder stroke time, not signed off in 14 days.

L Monthly Operations Report Novenber 1980 Page Three t

D.

CHA'iGES, TESTS AND EXFERIICITS CARRIED CUT WITHOUT CC!t4ISSION r

APPROVAL Procedure Descrintion EEAR FC-79-133 Installed a drain line from the Heater Drain Tank sa=ple coil to a floor drain to prevent water frem getting into the Heater Drain Pump suction piping wells.

EEAR FC-80-5 Replaced the Steam Generator Lower Accident Support Reds with newly designed reds.

EEAR FC-79-lk

. Replaced the Main Feedvater Pump R+circu-lation Valves (FCV-1151A/B/C) with a nev valve design.

. DCR FC-79-174, Part II Cable separation of blocking valves HCV-150 and HCV-151/ completed as designed.

DCR-79-172 Subcooled Margin Monitor / completed as designed.

DCR FC-79-17h, Part I Pressurizer Backup IIeater Centrol Modifi-caticn/ completed as designed.

DCR FC-78-56 Alternate Shutdown Panel /ccmpleted as designed.

DCR FC-79-173 Direct Indication of Power Operated Relief Valves and Pressuricer Spray Valves /com-pleted as designed.

SRDC0 76-55 Spent Fuel Pool Filter and Demineralizer Shielding /ccepleted as designed.

SRDC0 80 45 Replaced solenoid valve en HCV-883A/ changed frem Valcor to Asco.

Electric Fire Pump Modification / completed DCR 77-32 per design.

DCR 80-117 Solenoid Changeout for HCV-884A/ completed per design.

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RESULTS OF LEAK RATE TESTS There were no leak rate tests performed in November.

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Monthly Operations Report November 1980 Page Four F.

CILUGES IN FIA'lT OPEPATING STAFF None G.

TRAINING November training included fire brigade, Emergency Procedures, E=ergency Notification System, Tech. Spec. changes, C.P.R.,

Safety Meetings and Radiation Protection training for Operations, Guards and M=.intenance.

H.

CHMiGES, TESTS XiD EXPERI'CITS F2 QUIRING NUCLEAR REGUIATORY CC:MSSION AUTHORIZATION PURSUANT TO 10CFR50 59 Iten #1 - Order for modification of license concerning Envircnmental Qualifications of Safety Related Electrical Equipment dated October 2h, 1980.

Item #2 - Amend =ent No. 53 censisting of changes related to Fire Protection Modification.

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'A a-Approved By

4 rl Manager-Fort Calhoun Station

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Menthly Operatiets Repcrt November 1930 Page Five II.

MAINT'i"JA'ICI (Significant Safety Related)

M. O.

Date L

Descriptien a

Corrective Action 7207 9-30-30 HCV-2908 von't operate with the key Cylinders were overhauled.

svitch.

7631 10-28-80 HOV kh5 indicates erratic control Replaced centro 11er and cali-when the centro 11er is moved.

brated per CP kh5 7666 10-30-80 RPS Matrix Relay A3-1 failed to Replaced AB-1 Matrix Relay and trip clutch power supplies PS-1 retested per ST-RPS-11.

and PS-3 during ST-RPS-11.

7561 10-29-80 FP-5 Jockey Pasp - Nipples on Replaced fitting, discharge check show signs of leakage.

765h 10-29-80 RC-133 Vilve leaking.

Tightened packing.

7623 10-29-80 FW-6 Sequence Timer not timing.

Replaced timer and retested.

7329 10-27-80 Spent Resin Transfer from Holding Completed per SP-WDS-14 Tank to cask.

7760 11-7-80 DG-1 Air Compressor quit pumping Replaced ccmpressor.

When it is hot.

7763 11-5-80 Inlet line to regulator broken off Replaced broken fitting, in regulator.

736h 10-13-80 CH-183 Rebuild Valve.

Completed per MP-RV-1.

7869 11-lh-80 Process Monitor RM-05hA in alert Added more shielding around and chemistry does not indicate the housing of RM-05hA.

activity present.

7558 10-21-80 HCV-88hA vill not close.

Installed new solenoid valve.

Tested Satisfactorily.

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