ML20009D424

Monthly Operating Rept for June 1981

ML20009D424
Person / Time
Site:	Fort Calhoun
Issue date:	07/15/1981
From:	Shoot R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20009D418	List: ML20009D415 ML20009D424
References
NUDOCS 8107240047
Download: ML20009D424 (6)

Text

n AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

UNIT Fort Calhoun #1 DATE July 15, 1981 COMPLETED BY R. W. Short TELEPHONE (402)S36-4543 June, 1981 MONm DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(Mwe-Net) 188.9 210.8 i

37 2

189.3 305.9 is 3

189.2 363.0 39 4-188.5 368.0 20 186.0 368.9 5

21 185.0 376.0 6

22 7j 185.8 422.3 23 g-225.3 24 435.4 9

293.5 434.5 25 to 305.2 439.0 26 305.7 441.0 27 12 305.9 441.0 28 305.1 440.0 13 29 34 303.9 439.9 39 306.1 15 3,

250.3 16 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the nearest whale nwgawatt.

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'8107240047 810715

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DRADOCK05000g

OPERATING DATA REPORT 50-285 DOCKET NO.

DATE July 15, 1981 COMPLETED BY R. W. Short TELEPHONE (402)536 4543 OPERATING STATUS I

Canoun Radon Unit No. I Nues

1. Unit Name:

2. Reporting Period:

dune, 1981 1500

3. Licensed Thermal Power (MWt):

501

4. Nameplate Rating (Gross MWe):

478 S. Design Electrical Rating (Net MWe):

501

6. Masimum Dependable Capacity (Gross MWe):

470

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' 4

9. Power Level To Which Restricted,If Anv (Net MWeI:

N/A

10. Reasons For Restrictions,If Any:

N/A This Month Yr.-to-Da t e Cumulative 720.0 4,343.0 68,064.0 i1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 720.0 4,210.0 53,988.3 0.0 0.0 1,309.5

13. Reactor Reserve Shutdown Hours 713.4 4,161.4 52,92l'.3

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0.0 0.0

~0.0

- 16. Gross Thermal Energy Generated (MWH) 744,754.5 4,096,843.5 63,815,083.8

17. Gross Electrical Energy Generated (MWH) 240,476.0 1,346,474.0 21,134,745.6

18. Net Electrical Energy Generated (MWH) 225,592.8 1,259,040.0 19,957,222.9_

19. Unit Senice Factor 99.1 95.8 77.8 99.1 95.8 77.8

20. Unit Availability Factor 65.5 60.2 64.2

21. Unit Capacity Factor (Using MDC Neti

22. Unit Capacity Factor (Using DER Net) 65.5 60.2 63.8 0.9 4.2 4.1

- 23. Unit Forced Outage Rate

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

Refueling, September 15, 1981, 4-7 Weeks 4

J

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

N/A

26. Units in Test Status IPrior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITI A L ELECTRICITY COMMERCIA L OPEl* 4 TION (9/77)

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a UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-235 UNIT NAME Fort Calhoun #1 DATE July 15, 1981 COMPLETED ilY R. W. Short REPORT MONTH June. 1981 TELEPHONE (402)536-4543 n.2 E.

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,.-oEM Licensee

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Cause & Corrective

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No.

Date g

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,g g 5 Event u?

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Action to

$5 5

j di g Report

• N0 Prevent Recurrence 6

81-05 810616 F

6.5 H

1 N/A MA MECFUN Cause:

Defective potentiometer in load limit control.

Corrective Action: Replaced potentiometer.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data II Maintenance or i st 2 Manual Scram.

Entry Sheets for Licensee C. Refueling 3-Automatic Scram.

Event ReporI (LER) File INUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Es ror (Explain)

Exhibit I - Same Source (9/77) 11-01her (F xplain)

1 Eefueling Infonration Fort Ca"?.a Jn - Unit No.1 Repore for the nonth ending Jun% 1981 1.

Scheduled date for ncxt refueling shutdcan.

September 15, 1981 2.

Scheduled d ee for restart following refueling.

November 15, 1981 3.

Will refueling or resumption of operation thereafter require a technical specification change or other lice.me amendment?

No a.

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

b.

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

No c.

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

August 1, 1981 4.

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

- 5.

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

6.

The number of fuel assemblies: a) in the core 133 asserrblies 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 assuming the present licensed capacity.

1985 Prepared by

(/Ag Date July 1,1981

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit 'Io. 1 June 1981 Monthly Operations Report I.

OPERATIONS

SUMMARY

The unit operated at power levels from 66 to 95% reactar power during June. One outage ocutrred on June 16, due to a failed t'trbine load limit potentiometer.

The unit was returned to service early June 17 Pleparation for the SRO examination for three candidates continued during June.

The Supervisor-Operations t.ttended a one day meeting at the :;c=bu2-l tion Engineering Facilities in Windsor, Conn. on Inadequate Core Cooling.

Surveillance tests and operational tests were performed.

No safety valve or PORV challenges occurred on the primary system.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency NONE B.

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 surveillance tests schedule. The following is a s e nry of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident,_

Deficiency OI-1325 ST-RM h CAE Sampler out of service.

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.t Monthly Operations Report June 1981 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT ColC4ISSION APPROVAL Procedure Description EEAR/DCR #FC-7hA-21 Steam Generator Blowdown Tie Ins./ Completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 since it functions to reduce the chance of an uncontrolled radioactive release due to a primary to secondary release.

SP-VA-80 Rydrogen Purge System Test This procedure did not constitute an unre-viewed safety question as defined in 10CFR50 59 since it is only a test to demon-strate the operability of the hydrogen purge system.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection the two operable op channels shows greater than 99% assurance that the 150 pound criterion is not being violated.

An unreviewed safety question as defined in 10CFR50 59 did not exist as this procedure only involves evaluating data from a surveil-lance test.

EEAR FC-60 45 RCP Cooling Pipe Replacement. Completed as designed.

This modification did not constitute an unre-viewed safety question as defined in 10CFR50.59 as it only involved replacing some of the reacter coolant pump cooling piping with stain-

.less steel rather than carbon steel piping using appropriate nuclear grade material.

FC-78-141 Seal Water Mod. for Cire. Water Pumps and Raw 72-17 Water Pumps.

These modifications did not constitute an unre-viewed safety question as defined in 10CFR50 59 as they only involved replacing and improving the seal water piping to the circulating water pumps and the rav vater pumps.

Monthly Opcrations Raport June 1981 Page Three D.

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

EEAR FC-81-53 Deletion of Clutch Power to Part Length CEDM's SRDC0 #81-37 An unreviewed safety question as defined in 10CFR50.59 did not exist as the operational method of operating rod drives was not changed.

The rods in question do not have clutches and could not have been affected in anyway.

E.

RESULTS OF LEAK RATE TESTS NONE F.

CHA5GES IN PLANT OPERATING STAFF Merl Core has been assigned as acting I&C and Electrical Field Supervisor.

Bruce Hickle has been assigned as acting Chemical & Rad. Prot.

Supervisor.

Tom Chapman has been assigned as acting Health Physicist.

G.

TRAINING Training for June at the Fort Calhoun Station included general employee training for both new and plant personnel, operator train-ing, monitor team training and Emergency Preparedness training for offsite Support Personnel.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59 NONE

%d,h kW Approved By ager 3 Fo'rt Ca3houn Station

Monthly Operations Report Pa.3e II.

MAINTENANCE (Significant Safaty Related)

M. O. #

Date Description Cor ective Action 10093 5-29-81 RM-080 is spiking into " Alert" Cleaned switch and contacts observed for h-days.

No other problems.

10h00 6-9-81 DG-2 DC pr. supply (normal supply Bad Ann. Card A-1 on A-37 ann.

replaced tripped and would not and fuse.

Installed new power reclose).

supply. Diesel remained operable, 9876 h-lh-81 Part Length Rod #18 drives in when Separated clutch power from cables not selected. Also drives in when going to CEDM's. Refer to EEAR l

selected and scving " Rod Block" FC-81-58 SRDC0 #81-37 l

switch to bypass.

102h3 5-19-81 Air sampler at left station (OAE) has After replacing filter & cartridge j

high flow.

problem could not be duplicated.

l 102h1 5-19-81 V0PT channel C reset demand push but-Replaced switch preformed ST-RPS-1 ton on CB h does not reset setpoints.

F.3 I

10019 h-28-81 Repair breaker and cable which feed Replaced cable & breaker CB-22 AI-41B.

checked for grounds none.

Returned to normal. See LER 81-03 M

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