ML19350D927

Monthly Operating Rept for Apr 1981

ML19350D927
Person / Time
Site:	Fort Calhoun
Issue date:	05/11/1981
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19350D926	List: ML19350D925 ML19350D927
References
NUDOCS 8105270166
Download: ML19350D927 (8)

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50-285 miT F rt Calhoun #1 DATE May 11, 1981 COMPLETED BY - T. L. Patterson TELEPHONE (402)S36-4413 MONE April, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe. Net) i 304.3 37 196.0

, 2 303.5 is 196.0 3 302.9 19 195.8 4 303.1 20 195.9 s 303.6 21 196.7 6 301.7 22 196.5 7a 301.4 23 195.6 8 301.4 24 194.5 9 300.7 25 194.7 to 296.8 26 194.4 i 27.3 27 196.1 12 0A 28 42.9

3 0.0 29 0.0 14 148.9 3o 67.8 15 191 1 3 16 191~.6 INSTRUCTIONS On this format. list the average daily unit power levelin MWe-Net for each day in the reporting montli.0 mpute to the nearest whole megawatt.

(9/77 )

8195270166

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OPERATING DATA REPORT DOCKET NO. 285 DATE May 11. 1981 COSIPLETED BY _T. L. Patterson TELEPHONE ._(402)536-4413 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Unit No.1- Notes '

2. Reporting Period: April , 1981

3. Licensed Thennal Pcwer (51Wt): 1500

4. Nameplate Rating (Gross alWe): 501

5. Design Electrical Rating (Net 31We): 478

6. Staximum Dependable Capacity (Gross SIWE): 501

7. Staximum Dependable C 1pacity (Net 51We): 470

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

, N/A

9. Power Level To which Restricted. If Any (Net 31We): N/A

10. Reasons For Restrictions. If Any: N/A 5

This 31onth Yr.-to.Date Cumulative 2,879.0 i1. Hours In Reporting Period 719.0 66,600.0

12. Number Of Hours Reactor Was Critical 618.9 2,746.0 52,524.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309'.= 5

14. Hours Generator On-Line 597.7 2,704.0 51,463.9

15. Unit Reserve Shutdown Hours 0.0 0.0 ^ 0.0 i 16. Gross Thermal Energy Generated (SIWH) 472,040.0 2,815,981.5 62,534,221.8 -

17. Gross Flectrical Energy Generated (SIWH) 152,236.0 936,054.0 20,724,325.6

18. Net Electrical Energy Generated (SIWH) 139,994.7 _ 877,398.8 19,575,581.7

19. Unit Service Factor 83.1 93.9 77.3

20. Unit Availability Factor 83.1 93.9 77.3

21. Unit Capacity Factor (Using alDC Net) 40.7 63.0 64.4 l 22. Unit Capacity Factor (U;ing DER Net) 40.7 63.0 64.0

! 23. Unit Forced Outage Rate 16.9 6.1 4.2

24. Shutdowns Scheduled Oser Next 6 31onths (Type. Date.and Duration of Each):

Refueling, September 15, 1981, 7 weeks

25. If Shui l> mn At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Teu Status (Prior to Commercial Operation): Forecast Achieved INIi! A L CRITICALITY --

INillAL ELECTRICITY CO\DIERCIT L OPER ATION l (9/77) ,

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DOCKET NO. 50-285 -

UNIT SilUTDOWNS AND POWER REDUCTIONS Fort Calhoun #1

• UN T N AME n.

DATE May ll, 1981 COMPLETED ilY T. L. Patterson REPORT MONTil April,1981 (402)S36-4413 TELEPIIONE

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-, .!E 3g Yk Licensee ,Eg he. Cause & Corrective No. Date g 3g ,g g 5 Event u? o3 Action to H $, 5 j iji g Repert a rE U fU Prevent Recurrence 6

81-03 810411 F 69.2 H 1 81-002 IE INSTRU Reactor shutdein to inspect-

-l Foxboro pressbre transmitters.

I 81-04 F 52.1 A 3 81-003 EC ELECON Electrical connection to breaker CB-22 burned through causing loss of power to D.C. panel AI-41B.

1 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions -

S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparatiwe of Data II Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG.

D Regulatory Restriction 4-Other ( Explain) 0161)

E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source 19/77) Il Other (Explain)

Refueling Information Ebrt Calhoun - Unit No.1 Report for the nonth ending April 1981 ,

l. Scheduled date for next refueling shutdown. September 15, 1981

2. Scheduled date for restart following refueling.- November 15, 1981

3. Will refueling or resumption of operation thereafter require a technical specification change or other No license amendment?

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 ycur Plant Safety Review Comi.ttee to deter-mine whether any unreviewed~ safety questions No are associated with the core reload.

c. If no such review has taken place, when is it scheduled? September 1, 1981

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

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 nu:rber of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 147

'[ c) spent fuel pool storage capacity 4R1 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. igac; Prepared by Date May 1, 1981

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OMAHA PUBLIC POWER DISTRICT .

Fort Calhoun Stat.fon Unit No. 1 April 1961 Monthly Operations Report I. OPERATIONS SU)DfARY Fort Caltoun operated at two steady state power levels during April (65% and 45%). An outage to perform maintenance activities including Foxboro transmitters occurred from April 11 through April 13. A reactor trip occurred on April 28 due to a loss of DC Panel AI-42B. The unit was resynchronized to the grid on April 13, 1981.

Simulator training at the Combustion Engineering facility in Windsor, Connecticut, was completed for 1981 during the first week of April. All operations personnel involved successfully completed the one week of simulator requalification training.

Preparations for the 1981 refueling outage continued.

The Supervisor-Operations attended a one day meeting in Windsor, -

Connecticut, on Emergency Procedure guidelines.

All required operational and surveillance tests were completed.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 81-002 During normal power operation at a nominal 65%

power, notification was received from the Foxboro Company that a potential defect may exist in certain transmitters manufactured by Foxboro.

The transmitters in question may have had a capac-itor installed in the amplifier that could fail l

due to heat. either during operation or after a l LOCA. Further, some of the transmitters may have had insulation installed that could become brittle after exposure to high radiation which may occur a.!:er a LOCA. Technical Specification 5.9.2(9) applies.

l B. CHANGES IN OPERATING METHODS None

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Monthly Operations Report April 1981 Page Two C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests are required by the Technical Specifications Section 3.0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a summary of the surveillance tests which results in Operations

. Incidents and are not reported elsewhere in the report:

Operations Incident aaficiency OI-1307 ST-ICI-2 Failed to perform test on schedule.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descr'7 tion SP-FAUD-1 Fuel Assembly Uplift Condition: Detection the two operable Ap 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.

l l SP-NFR-1 Fuel Receipt Procedures.

This procedure provides for the safe and orderly l receipt, handling, inspection, and storage of new fuel. Performance of this spucial procedure does not constitute an unreviewed safety question l per 10CFR50.59 as the fuel handling equipment is tested prior to use, no loads are taken over spent fuel, and the fuel receipt crew is given specific l

training prior to th" evolution. Applicc' ale Technical Specifica. sns were complied with.

SP-CTPC-1 Core Thermal Power Calculation - NSSS Calorimetric.

This procedure is a calculational check of cali-metric accuracy and involves no control manipulation or system changes. Checking helps assure compliance with license power limits. An unreviewed safety question as defined in 10CFR50.59 did not exist since this procedure is a calculational check of calimetric accuracy and involvad no control mani-pulation.

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s Monthly Oparations Rzport April 1981 Page Three E. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING Training for April consisted of general employee training and retraining (badge trainirg). Systems training for all plant personnel. Monitor Team training, Safety Meetings and requali-fication training was scheduled for' operators.

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

Amendment No. 58, which adds a requirement to maintain a safeguard continge'...y plan.

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Monthly Operations Report April 1981 Page Four II. MAIIITETANCE (Significant Safety Related)

M. O . # Date Description l Corrective Action 9640 3-;.9-81 Primary Air DG-2 leak on solenoid. Cleaned regulator and stopped leak.

6421 7-9-80 -DG-1 Control Panel - smoke out of Replaced immersion heater ,

panel. ':* transformer.

8625 1-16-81 HCV-401A excessive stroke time. Replaced relay - retested satisfactorily.

9575 3-22-81 Overhaul AC-10-B Raw Water Pump. Completed.

9807 4-6-81 Foxboro transmitter check and Checkad transmitters and change amplifiers. changed amplifiers.

10038 4-30-81 Rod 40 stuck. Replaced drive mechanism, rod was tripable.

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