ML20023C603

Monthly Operating Rept for Apr 1983

ML20023C603
Person / Time
Site:	Fort Calhoun
Issue date:	05/12/1983
From:	Mathews T OMAHA PUBLIC POWER DISTRICT
To:
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ML20023C598	List: ML20023C597 ML20023C603
References
NUDOCS 8305170470
Download: ML20023C603 (11)

Text

F l

r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Calhoun Statior DATE _Ma_y 12, 1983 COMPLETED BY T. P. Matthews TELEPilONE (402)536-4733 MONE April, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) iMWe-NetI t

0.0 i7 283.5 2

0.0 i8 284.2 3

0.0 19 297.9 4

0.0 20 351.9 5

0.0 2i 351.5 6

10 4 22 389.1 7

34.8 412.5 23 8

98.1 24 423.7 9

157.4 25 431.9 in 175.6 407.8 26 Ii 176.9 353.9 27 177.6 23 352.8 13 176.5 352.9 29 34 174.9 353.2 3o 15 182.2 33 16 277.2 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe Net for each day in the reporting anonth. Compute to the nearest whole megawatt.

tiu?7) 8305170470 830512 PDR ADOCK 05000285 R

PDR

OPERATING DATA REPORT 50-285 DOCKET NO.

DATE - May 12, 1983 COMPLETED 11Y T. P. flatthews TELEPilONE (402)536-4733 OPERATING STATUS Fort Calhoun Station Notes

1. Unit Name:

April,1983

2. Reporting Period:

3. Licensed Thermal Power (MWt):

1500 501

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

478 501

6. Maximum Dependable Capacity (Gross MWe):

478

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Lesel To which Restricted.lf Any (Net MWe):

N/A

10. Reasons For Restrictions,if Any:

None This Month Yr.-to Date Cumulative i1. Hours Iq Reporting Period 719.0 2,879.0 84,120.0

12. Number Of Hours Reactor Was Critical 655.0 655.0 64,765.5

13. Reactor Resene Shutdown Hours 0.0 0.0 1,339.5

14. Hours Generator On Line 574.5 574.5 63.522.0

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 567,342.9 567,342.9 78,183,891.3 17 Gross Electrical Energy Generated IMWH, 172,366.0 172,366.0 25,907,699.5

18. Net Electrical Energy Generated (MWH) 160,299.6 160,299.6 24.490.334.0

19. Unit Senice Factor 79.9 19.9 75.5

20. Unit Asailability Factor 79.9 19.9 75.5

21. Unit Capacity Factor (Using MDC Net) 40.6 11.6 63.2 46.6 11.6 61.2

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0.0 0.0 3.9

24. Shutdowns Scheduled Oser Nest 6 Months tType. Date,and Duration of Each1:

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

26. Units in lest Status t Prior to Commercial Operation):

N/A Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICI fY COMMERCI AL OPER A llON yli' ? >

50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Fort Calhoun Station DATE May 12, 1983 _

COMPLETED BY T. P. Matthews REPORT MONTH April. 1983 TELEPHONE (402)S36-4733

_ "h E

5g 3

4 $E Licensee Eg je, Cause & Corrective No.

Date g

3g ji&

Even 37 gl Action to

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Report a mO o'

Prevent Recurrence y=

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Q 82-06 821206 S

135.5 C

4 N/A XX XXXXXX 1982/1983 refueling outage com-menced December 6, 1982.

I 83-01 830407 S

9.0 B

4 N/A XX XXXXXX Unit taken off line to perform turbine overspeed tests April 7, 1983.

The unit was placed back on line the same day.

t i

2 3

4 i: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A Equipment Failure (Explain)

I4f anual for Preparation of Data B41aintenance of Test 24f anual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Esent Report t1.1 R) File iNUREG-D-Regulatory Restriction 4 Other (Explaini 0161)

ILOperator Training & License Examination F-Adnunistrative 5

G-Operational Eiror i E xplain)

Exhibit I - Same Source 08/77)

II Other (E xplain;

m Refueling Infor: ration Fort Calhoun - Unit No.1 Feport for the conth ending April 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 amendnent?

Yes a.

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

A Technical Soecification Change b.

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

c.

If no such review has taken place, wtien is it scheduled?

4.

Scheduled date(s) for submitting proposed licensing Methodology - Dec. 1983 action and support information.

Tech. Specs.- Feb. 1934 5.

Important 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 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728 7.

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

1985 Prepared by M

Date May 2, 1983 U

V' 4

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

6'5 RATIONS

SUMMARY

Fort Calhoun Station entered April on its way back from a four month refueling outage.

The reactor was made critical April 2,1983, for low power physics tests which lasted through April 5,1983.

Testing was delayed one day while repairs were made to a reactor control element drive mechanism.

The unit was placed on line April 6, 1983, and power raised to warm the turbine for testing.

On April 7,1983, the unit was taken off line to perform turbine overspeed tests and steam valve leak tests.

These tests are normally performed while shutting down for refueling outages but were postponed due to turbine failure on December 3, 1982.

The unit was placed back on line April-7,1983, operating at 45% power April 9-15, 1983; 66% power April 19-22, 1983, while reactor incore instrumentation corrections were made.

Power varied from 90% to 96%

April 22-26, 1983, when it was reduced to 80% for testing of reactor core characteristics.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS None 8.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B were performed in accordance with the annual surveil-lance test schedule.

The following is a summary of the surveillance tests which resulted in Operation Incidents and are not reported elsewhere in the report:

Operation Incidents Deficiency 01-1674 ST-PL-1 During the performance of ST-PL-1 it was discovered that the LT-10lX transmitter as well as the LRC-10lY controller had been operating outside calibration tolerances.

F Monthly Operations Report April, 1983

'Page Two C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (continued)

Operation Incidents Deficiency 0I-1673 ST-RPS-6 During the performance of 'ST-RPS-6 the following transmitters were found to be out of calibration tolerance:

LT-B/901 and LT-C/904 (Steam Generator RC-2B Level).

01-1684 ST-RPS-3 During the performance of ST-RPS-3 the reactor coolant flow channel calibration transmitters A/dpT ll4X and A/dpT ll4Y were found to be out of calibration specifications.

01-1677 ST-FW-3 During the performance of ST-FW-3 D/911 and B/912 were found out of calibration.

01-1700 ST-DC-2 During the performance of ST-DC-2 breaker DC3-1 was found to be bad.

D.

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

Package Description / Analysis EEAR/FC-82-140 Qualification of PCV-2909/2929/2949/2969.

This modification ensures proper qualification of PCV-2909/2929/2949/2969.

The installation of this modification does not alter the fail safe mode of the PCV's since this modification will be completed during cold shutdown.

This modification has no adverse effect on the safety analysis.

EEAR/FC-82-176 Improved Reactor Coolant Gas Vent System.

This modification provides for relocation of pressurizer vent valve RC-167 and flange to allow for rapid venting during draining and filling of the reactor coolant sys-tem. Modified vent configurations will be the same as the one existing before the installation of the reactor coolant gas vent system except modified vent path is through RC-102 instead of RC-126.

This modification will increase plant safety and consequently, has no adverse effect on the safety analysis.

Monthly Operations Report April, 1983 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis EEAR/FC-81-32 TCV-202 Modification.

The purpose of this modification was to modify TCV-202 in order to eliminate leakage and to allow for improved valve maintenance.

This modification will increase-plant safety and consequently, has no adverse effect on the safety analysis.

EEAR/FC-83-43 Pressurizer Level Instrumentation Nozzle Modification.

The purpose of this modification was to modify the pressurizer level indication nozzles to allow better level indication during power operation.

No new system was involved nor was the operation of any system altered.

Only a minor modification of the existing equipment was installed.

This modification has no adverse effect on the safety analysis.

EEAR/FC-80-99 Replacement of FCV-326, NAMC0 EA180 Series Limit Switches, and ASCO Solenoid Valve.

The purpose of this modification was to replace existing FCV-326, NAMCO EA180 Series Limit Switches, with new ones.

This modification is a replacement of existing valve with a better valve. This modi-fication has no adverse effect on the safety analysis.

EEAR/FC-82-146 Installation of Two Flanged Spool Pieces on HCV-335.

The purpose of this modification is to install two flanged spool pieces on HCV-335. This modification has no adverse effect on the safety analysis.

EEAR/FC-79-129 Replacement of Steam Generator / Reactor Coolant Instrument Root Valves.

This modification provides for the replacement of leaking instrument root valves (from packing or internal leakage) on the secondary side of the steam generator and the primary side of the reactor coolant system.

This modification provides replacement of the same type valves.

This modification has no adverse effect on the safety analysis.

l

Monthly Operations Report April,.1983 Page Four D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis

~

DCR 74B-41 Pressuriier Mini-Spray Valves RC-131 & 133 Modification.

The purpose of this modification was to replace the pressurizer mini-spray valves RC-131 & 133.

This modification provides a better type valve that will provide a better throttling control of continuous low flow.

This modification has no adverse effect on the safety analysis.

i E.

RESULTS OF LEAK RATE TESTS The 1982 refueling outage Type B and Type C local leak rate test summary report is complete and will be forwarded to the Nuclear Reactor Regula-tion Branch per 10CFR50, Appendix J.

F.

CHANGES IN PLANT OPERATING STAFF i

None G.

TRAINING The Fort Calhoun Station Unit No.1 annual training program was implemented as scheduled on April 11, 1983, when the Cycle 8 outage was completed.

The programs included general employee, maintenance, chemistry and radiation protection trainees, NRC license requalification, fire brigade and non-license operator training.

i H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59.

i Amendment No. 71 Made permanent the temporary minimum temperature requirement for secondary pressure testing.

Amendment No. 72 Updated snubber information regarding accessibility and type.

Amendment No. 73 Deletes the interim special Technical Specification regarding operation with less than 75% of incore detector strings operable.

Monthly Operations Report Aprila 1983 Page Five II.

MAINTENANCE M.0. #

DATE DESCRIPTION CORRECTIVE ACTION 19311 3/17/83 HCV-1045A indicator lights do Readjusted limits.

Cycled valve and do not work.

worked okay.

19494 3/26/83 Liquid Radiation Release Monitor Replaced Q101 and Q103 in 16 VDC RM-055 failed.

power supply.

17548-2/26/83 Replace containment pressure Replaced switches and calibrated.

switch A/PC-742-1 left and right out of specification.

15904 3/20/83 Change oil and clean and inspect Completed per MP-RC-3-1.

RC-3A.

19334 3/22/83 RC-38 clean, inspect and change Completed per MP-RC-3-1.

oil on reactor coolant pump motor.

15916 3/20/83 RC-3D clean, inspect and change Completed per MP-RC-3-1.

oil on reactor coolant pump motor.

11068 2/2/83 RC-3C motor upper thrust bearing Performed sensor calibration on temperature T-3146 is reading computer for TRD (3146).

high.

12456 10/27/82 DG-2183/MES failure to get Calibrated speed switch CP-6148.

proper operation of relay 105X in the diesel control panel.

19405 3/23/83 AC-3C component cooling pump Replaced outboard bearing on motor.

running hot.

14677 3/17/63 Metrascope-CEA #10 indicating Tightened loose terminal in patch out of group alignment.

panel.

18782 2/25/83 HCV-150 remove motor and repack Completed, grease in gear box.

18783 2/24/83 HCV-151 remove motor and repack Completed.

grease in gear box.

19188 3/16/83 Relay 829 in cabinet AC/DC-2 Replaced relay coil and contacts.

behind CB-1 burned up.

19137 3/17/83 A31 120V power indicator reading Changed PAN alarm 70-ARI.

erroneously.

19823 4/5/83 HCV-884A has green light when Adjusted limit switches.

switch is turned open.

Monthly Operations Report 1

April,1983 Page Six

.1 l

II. ' MAINTENANCE (continued)

M.0. #

DATE DESCRIPTION CORRECTIVE ACTION

'18887 3/11/83 Check HCV-1108A&B for proper HCV-1108B okay.

Changed splice on splices.

HCV-1108A.

15140 3/8/83 FW-10 S2-2 sequence timer timed Exercised unit and retested per out improperly.

MP-EE-20.

19460 3/ 31/ 83 Sub cooled margin monitor B not Replaced multiplexer integrated i

working.

circuits.

i 19654 4/6/83 When HCV-2938 is operated, a DC.

Installed variator across solenoid ground on #2 D.C. Bus appeared.

wiring in AI-1288.

19780 4/2/83 RPS "B" wide range channel Adjusted to 820 VDC calibrated per reads low.

CCP-B/NI-002.

1 19612 3/30/83 Sigma for PCV-2969 has failed.

Replaced photo diode and recali-brated sigma (MP-SIGMA-1).

19656 3/31/83 PIC 2909 high pressure LED Replaced photo diode for high alarm fails.

and recalibrated sigma (MP-SIGMA-1).

15268 3/28/83 EE-8H, 8J, 8K & 8L inverters Made wiring changes and tested.

A, B, C and D rewire inverters.

i 15660 1/2/83 Perform visual inspection of Completed per MP-RC-2-3.

RC-28 primary side.

15659 1/2/83 Perform visual inspection of Completed per MP-RC-2-3.

RC-2A primary side.

I 15465 12/18/82 Area monitor RM-086 meter is Replaced meter.

Calibrated.

j sticking.

15332 3/3/83 Raw Water Strainer AC-12B Completed.

replace piping from HCV-2805 to both 3" flanges on strainer.

15331 3/8/83 Raw Water Strainer AC-12A Completed.

replace piping from HCV-205A to both flanges on AC-12A strainer.

15651 1/17/83 Perform RC-2B secondary visual Completed per MP-RC-2-4.

inspection.

15652 1/18/83 Perform RC-2A secondary visual Completed per f1P-RC-2-4.

l inspection.

15990 3/18/83 AC-4A shutdown cooling heat Completed per MP-AC-13.

i exchanger - eddy current test.

• * ~ '

• Monthly Operations Report April,1983 Page Seven II.

MAINTENANCE (continued)

M.0. #

DATE DESCRIPTION CORRECTIVE ACTION 19971 4/15/83 Charging Pump CH-1A CVQS leaking

. Replaced-pump, installed new gaskets into packing cooling tank with and pistons.

demineralized water isolated.

19655 4/19/83 RC-133 repair / replace packing Per repair procedures.

gland stud.

p.

W. G. Gates Manager Fort Calhoun Station

,