ML20076J180

Monthly Operating Rept for May 1983

ML20076J180
Person / Time
Site:	Fort Calhoun
Issue date:	06/14/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-145, NUDOCS 8306200358
Download: ML20076J180 (11)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Statio' DATE June 14. 1983 COMPLETED BY T. P. Matthews TELEP110NE (402)536-4733 MONE flay,1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1MWe-Net I i 353.8 7 450.4 2 344.9 i8 451.9 3 12.3 19 450.4 4 0.0 20 455.9 5 95.0 21 459.7 6 294.3 22 458.7 7 444*7 23 457.3 _

8 445.7 24 456.4 9 446.9 25 457.4 I go 446.9 457.5 26

, 447.1 456.3 27

32 445.9 455.8 28 l

33 443.2 29 455.1 34 387.9 453.3 3o I5 451.8 3i 454.6 16 451.6

! INSTRUCTIONS l On this format,hst the average daily unit power leselin \1We Net for each day in the reportine inonth. (:oinpure tu l the nearest whole megawatt.

l 8306200358 830614 - L -

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PDR ADOCK 05000285 R PM (h2 f

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE June 14, 1983 COMPLETED BY _T. P. Matthews TELEPHONE (402)S3f-4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station N"

2. Reporticg Period: flay,1983

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity IGross MWe): 5

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To Which Restricted. lf Anv INet MWe): N/A

10. Reasons For Restrictions. If Any: None This Month Yr..to.Date Cumulative II. Hours In Reporting Period 744.0 3,624.0 84,865.0

12. Number Of Hours Reactor Was Critical 711.4 1,366.9 65.476.9

13. Reactor Resene Shutdown Hours 0.0 0.0 1.309.5

14. Hours Generator On.Line 693.5 1,268.0 64.265.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Ihermal Energy Generated (MWH) 975,283.0 1,542,625.9 79,159,174.3

17. Gross Electrical Energy Generated (MWH) 312,166.0 484,532.0 25,908.011.3

18. Net Electrical Energy Generated (MWH) 296,228.5 456,528.1 24,786,562.5

19. Unit Service Factor 93.2 34.9 75.7

20. Unit Availability Factor 93.2 34.9 75.7

21. Unit Capacity Factor IUsing MDC Neti 83.3 26.4 63.3

22. Unit Capacity Factor f Using DER Net) 03*3 26*4 61.4

23. Unit Forced Outage Rate 6.8 3.8 3.9

24. Shutdowns Scheduled Oser Nest 6 Months iTy pe. Date,and Duration of Eacht:

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

26. Units in Test Status (Prior to Commercial Operation): N/A Forecast Achiesed INITi \ L CRITICALITY INITIAL ELECIRICirY CO\l%IERCI \L OPERTilON pt 7

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE June 14. 1983 REPORT MONTH May, 1983 COMPLETED BY T. P. Matthews TELEPHONE (402 M36-4731 3 -

e ei 3 w: 5 c '1,

,., .2 _e E , s 's Licensee g-r, a Cause & Currective N. i . 1) ate i ~@

2 3, 55$ Event 7y SU S.3 Action to

$E $ j if> j Reporia U Prevent Recurrence d

83-02 830503 F 50.5 B 4 N/A MA TURBIN Generator off-line from 5/3 to 5/5 to add balance weight to turbine and repairs to FCV-1101, RC-133, RTD A-122H, and RTD D-112H.

I 2 3 4 F: Forced Reason: Method: Exhibit G . Instructions S: Ssheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data B4taintenance of Test 2 Manual Scram. Entr> Sheets for Licensee C Refueling 3-Automatic Scram. Event Report t LER) File (NUREG-I)-Regulatory Restriction 4 01her (Explaini 0161) 1 -Operator Training A 1.icense Examination F-Adnunistrative 5 G-Operational E:ror (Explain) Estubit I Same Source l'8/77) Il Olhe r (E splain)

a Refueling Information Fort Calhoun - Unit No. 1 ,

Report for the nonth ending May 1983 -

1. Scheduled date for next refueling shutdown. March 1984

2. Scheduled date for restart following refueling. May 1984

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 these be?

4 A Technical Specification Chance

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cm mittee to deter-mine whether any unreviewed safety questions are associated with the core reload.

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

4. Scheduled date(s) for submitting proposed licensing fiethodology - October 1983 action and support information. Tech. Specs.- February 1984

5. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

6. The number of fuel assemblies: a) in the core 13, asse:rblies l

b) in the spent fuel pool pr;c; c) spent fuel pool l storage capacity an1 l d) planned spent fuel pool

. storage capacity 7pn

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1onc; Prepared by k/ a-ni/) Date June 2. 1983 l

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 May, 1983 Monthly Operations Report -

I. OPERATIONS

SUMMARY

Fort Calhoun Station entered May at 80% power only to start down May 2, 1983, for a two-day outage May 3-5. During the outage, the following eouipment was repaired: a leaky feedwater heater manway, a feedwater flow control valve, two RTD's on the reactor coolant system hot legs, balance weight added to the turbine, turbine differential expansion detector adjusted, and a pressurizer mini-spray valve which required the RCS to be depressurized to 1150 psia. The Station was up to 97%

power by May 7 and increased to a nominal 100% power May 20.

Fuel inspection for the 00E extended burnup study on spent fuel commenced May 11, 1983. In this eight week inspection, selected fuel pins will have eddy current tests, profilometry tests, oxide thickness and shoulder gap measurements.

Annual licensed operator requalification training at Combustion Engineering simulator in Windsor,. Connecticut, started May 9, 1,983.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS l Surveillance tests as required by the Technical Specifications Section

! 3.0 and Appendix B were performed in accordance with the annual sur-veillance test schedule. The following is a summary of the surveil-lance tests which resulted in Operation Incidents and are not reported elsewhere in the report:

l Operation l

Incidents Deficiency 01-1634 ST-CONT-7 During the performance of ST-CONT-7

several jumpers were installed to l provide VIAS contact in the control string of HCV-1749 and V-6. These jumpers were not entered into the l

jumper log.

Monthly Op rations Raport May, 1983 Page Two Operation Incidents Deficiency 01-1678 ST-RM-4 During the performance of ST-RM-4 sampler QAA was inadvertently left in the off position.

01-1714 ST-ISI-CC-3 Discharge pressure on "B" component cooling pump fell into the high required action range.

01-1717 ST-FP-10 During the performance of ST-FP-10, F.1 halon bottle 55467 EH was low on pressure.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL System Acceptance Committee Packages for May, 1983:

Package Description / Analysis EEAR/FC-79-181C Instrument Tubing for Transmitter C/LT-911 Steam Generator Wide Range Level Indication.

This modification is for the removal of the existing tubing support. Calculations assure that removal of this restraint will not cause undue strain on the tubing and preclude the occurrence of an accident.

This modification has no adverse effect on the safety analysis.

EEAR/FC-81-131 Corrosion on Vacuum Pump for RM-057.

i This modification provides for the installation of a moisture separator and drain trap on the suction line of Radiation Monitor RM-057. This modification will increase plant safety and consequently has no adverse effect on the safety analysis.

EEAR/FC-82-90 PVC Acid Drain Line.

This modification provides for replacement of the i

existing acid drain pipe in the water plant. This I modification has no adverse effect on the safety l analysis.

l EEAR/FC-82-46 FW-10 Mechanical Trip Linkage Position Indication.

This modification provides for the installation of a limit switch alarm on the back pressure trip of FW-10. This modification will increase plant safety and consequently has no adverse effect on the safety analysis.

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Monthly Operations Report May, 1983 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis l EEAR/FC-80-99 FCV-326 Modifications (Spool Piece Only).

Part I This modification installs flanged spool pieces.

This modification has no adverse effect on the safety analysis.

EEAR/FC-79-177 Containment Hydrogen Monitor / Securing Containment Integrity.

This modification provides the installation and test instructions for installing solenoid control boxes for HCV-820A, 821 A, 820B, 821B, 8838 and 8848. This modification will increase plant safety and con-sequently has no adverse effect on the safety analysis.

EEAR/FC-79-28 Auxiliary Steam Trap Access Platform.

This modification provides for the installation of a platform in the turbine building to allow for easier access to the auxiliary steam trap. This modification has no adverse effect on the safety analysis.

.s EEAR/FC-80-113 Fire Detector Access Platform.

This modification provides for the installation of a platform in the auxiliary building Room 69 to allow for easier access to fire detectors. This modification has no adverse effect on the safety analysis.

EEAR/FC-81-ll4 Replacement of Clarifier Softener Valve.

This modification provides for the replacement of the clarifier softener desludge valve. 1his modifica-tion has no adverse effect on the safety analysis.

l DCR/76-63 FH-12 Limit Switches.

l This modification allows for the spent fuel handling i machine to travel in a larger periphery in order

that the hook may reach the new high density spent

! fuel assemblies. This modification has no adverse effect on the safety analysis.

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Monthly Op: rations Report May, 1983 Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis EEAR/FC-83-41 Yokesleeve for HCV-2938.

This modification provides for the replacement of the yokesleeve on HCV-2938. This modification has no adverse effect on the safety analysis.

EEAR/FC-81-184 Replacement of FW-273 and FCV-ll72.

This modification provides for the installation and test procedures for replacing existing valves FW-273 and FCV-ll72 with new ones. This modifi-cation has no adverse effect on the safety analysis.

EEAR/FC-79-171 PORV Partial Drain of Loop Seals and Restraints.

This modification provides for the analysis of the pressurizer safety relief valves at Fort Calboun Station and necessary, modifications. This modification will increase plant safety and consequently has no adverse effect on the safety analysis.

EEAR/FC-81-119 Stator Cooling Conversion.

This modification ensures the proper installation of instruments required to provide dual indication of coolant ficw and appropriate contacts for alarms and unit trip. This modification has no adverse effect on the safety analysis.

EEAR/FC-81-154 Replacement of FCV-1101 and FCV-1102.

This modification provides for removal, installation -

i and testing of the replacement FCV-1101 and FCV-1102 valves. This modification will increase plant safety and consequently has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF None l

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Monthly Op: rations Report May, 1983 Page Five G. TRAINING Training for May,1983, included Simulator Training at Combustion Engineering for licensed operators; and systems, math and theory for non-licensed operators. Fire brigade training for operations and security personnel was also conducted. Systems training for maintenance personnel and geaeral employee training (initial and refresher) for personnel requiring access to the Fort Calhoun Station was conducted.

H. CHANGES, TESTS AND EXPERIEMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59.

None II. MAINTENANCE M.0. # DATE DESCRIPTION CORRECTIVE ACTION 19518 3/25/83 HCV-1388B valve stroke time too Replaced o-rings and set valve high per ST-ISI-FW-1. stroke; retested per ST-ISI-FW-1.

20125 4/21/83 RM-061/62 pump will not turn. Replaced pump.

15893 1/17/83 RC-2B replace secondary manway Completed per MP-RC-2-2-B.

cover.

15889 1/18/83 RC-2A replace secondary manway Completed per MP-RC-2-2-B.

Cover.

15890 1/14/83 RC-2A remove secondary manway Completed per MP-RC-2-5-A.

Cover.

15852 12/13/83 HE-1A polar crane; perform Completed per MP-HE-1.

annual inspection.

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15840 2/14/83 CH-208 is leaking through. Completed per MP-RV-1.

f 15836 3/7/83 FW-19 emergency feedwater tank; Completed.

sandblast and paint interior.

18393 2/3/83 Breaker 184A line bus has arcing Completed per procedure.

splatters from bus bar.

15822 3/11/83 51-177 containment spray isola- Checked and repacked valve.

[

tion valve operates extremely hard.

15820 3/25/83 HCV-333 has a bonnett leak. Completed per MP-CV-CALMEC-l.

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Monthly Operations Report May, 1983 Page Six II. MAINTENANCE (continued)

M.0. 4 DATE DESCRIPTION CORRECTI/E ACTION 15809 2/17/83 AC-284 leaks through. Completed per maintenance order procedure.

15808 2/17/83 AC-283 leaks through. Completed per maintenance order procedure.

18908 3/4/83 Replace seal ring on station Completed, batteries.

I 18000 1/14/83 Replace "C" fission chamber. Installed per MP-PR/WRD-1.

18372 1/29/83 Containment particulate monitor Replaced detector.

(RM-050) came into alert after paper changed and will not i decrease.

Af,/.

W. G. Gates Manager Fort Calhoun Station

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Omaha Public Power District 1623 Harney Omaha Nebraska 68102 402/536 4000 June 14, 1983

! LIC-83-145 l

Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docke t No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the May Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, y i\

W. C. qhnes Divisidn Manager Production Operations WCJ/TLP:jmm Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center NRC File I l 455'24 Employmentgth Qual 0pportunity

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