ML20062M880

Monthly Operating Rept for Nov 1981

ML20062M880
Person / Time
Site:	Fort Calhoun
Issue date:	12/09/1981
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20062M868	List: ML20062M864 ML20062M880
References
NUDOCS 8112180293
Download: ML20062M880 (7)

Text

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AVERAGE DAILY UNIT POhER LEVEL DOCKET NO. 50-285 WIT Fort Calhoun #1 DATE December 9. 1981 COMPLETED BY R. W. Short f (402)536-4543 TELEPHONE 4

yg3m November, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net) (MWe Net)

, 0.0 0.0 37 ,

J 7

0.0 18 0.0 '

i- 3 0.0 39 0.0 '

4 0.0 ,, 0.0

5 0.0 21 0.0

} 6 0.0 2, 0.0 7 0.0 23 0.0 g 0.0 24 0.0 .;

i 9 0.0 25 0.0

!_ 30 0.0 26 0.0 i

i 0.0 27 0.0

. 12 0.0 ,g 0.0 i 13 0.0 ,, 0.0

i4 0.0 39 0.0

j. 15 0.0 3, I6 .0.0 j.

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INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reportmg month. Compute to i the nearest whole megawatt.

(9/7 'l 1

l 8112180293 8 QDRADOCK050 4

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T OPERATING DATA REPORT .

4 DOCKE T NO. _ 50-285

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DATE _ December 9, 1981 CO.\lPLETED BY R. W. Short '

TELEPHONE (4021536-4543 OPERATING STATUS

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

2. Reporting Period: November, 1981

3. Licen ed Thermal Power (.\lht): 1500 '

! 4. Nameplate Rating (Gross alWe):

I

. 5. Design Electrical Rating (Net SIWE):. ' 470

6. Stasimum Dependable Capacity (Gross stWe): 501 7, Alasimum Dependable Capacity (Net AlWe): 4M

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

N/A I' 9. Power Lesel To which Restricted,If Anv (Net 31We): N/A l

10. Reasons For Restrictions,if Any: N/b s

J This alonih Yr..to-Date ~ Cumulative i i1. Hours in Reporting Period 720.0 8,016.0 71,737.0

12. Number Of Hours Reactor Was Critical 0.0 6,130.6 55. 9 6.9

13. Reactor Reserve Shutdown Ho.as 0.0 0.0 1 ,1 0 T T i 14. Hours Generator On-Line 0.0 6,080.3 54,840.2

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

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16. Gross Thermal Energy Generated (%IWH) 0.0 6,728,000.2- 66,446,240.5

17. Gross Electrical Energy Generated (NIWH) 0.0 _ _ _ _

2,200,498.0 21,988,/69.6

] 18. Net Electrical Energy Generated (31WH) 0.0 ,2,069,985.6 20,/68,166.5

19. Umt Senice Facto 0.0 75.9 76.4

20. Unit Availability Factor 0.0 75.9 .76.4

j. 21. Unit Capacity Factor (Using alDC Net) 0.0 53.8- 63.2 .[

i 22. Unit Capacity Factor (Using DER Net) 0.0 53.8 62.9 7 23. Unit Forced Outage Rate 0.0 2.9 3.9 j 24. Shutdowns Scheduled Oser Next 6 Slonths IType. Date.and Duration of Each t:

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Decem W M, M --

26. Units in Test Status (Praor to Commercial Ope ation): N/A Forecast Achiesed I

INITI A L CRITICALITY . . _ _ -.- --

j INillA L ELEC1RICITY CO\lilERCI \ L OPER A TION _

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DOCKET NO. 50-285

- UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun #1-UNIT N AM E DATE December 9. 1981 REPORT MONTil November, 1981 COMPLETED HY Short .

TELIPilONE )536-454J

~5 P$ Y E E s s'Ade f .3,0 Licensee 5 t, g% Cause & Corrective No. Date g 3g j j g5 Event u? a3 Attion to

'H

$5 5 }*isg Report # SU ' Psevent Recurrence Q

81-06 810918 5 1754.1 C _1 N/A N/A N/A Reactor shutdown for annual refueling and maintenance outage.

I 2 3 4 F: Forced Reason: Method: Exhibit G. instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Repost (LI:RI File tNUREG-D-Regulatory Restriction 4 Other (Explain) 01611 E-Operator Training & License Examination F-Administrative ".

G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

Refueling Information

-Fort Calhoun - Unit No. 1 Report for the ncnth ending November 1981.. ,

1. Scheduled date for next refueling shutdown. De'cember 1. 1982

2. . Scheduled date for restart following refueling. Marci,1. 1933

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3. Will refueling or resumption of cperation thereafter require a technical specification change or other license anendnent? Yes

a. If answer is yes, what, in general, will 4

these be?

A Technical Specification change.

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b. _If arsaur is no, has the reload fuel design and core configuration been revie ed by your Plant Safety Paview Comittee to deter-mine whether any unreviewed safety questions -

are associated with the core reload.

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

4. Scheduled date(s) for submitting proposed licensing action and support infor ration. September 1. 1982

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

6. We ntsrber of fuel assenblies: a) in the core 133 assmblies b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483

7. h e projected date of the last refueling that can be discharged to the spent fuel pool asstming the present licensed capacity. 1985 Prepared by Date December 3, 1981

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 Nove=ber 1981 Monthly Operations Report I. OPERATICNS

SUMMARY

The Operations staff at Fort Calhoun Station participated in the scheduled Refueling Outage tests and Maintenance activities.

The staff co=pleted a verification valkdown of Fort Calhoun piping and instrumentation drawings to support a timely update of drawings to be used for Fort Calhoun startup.

Three new e=ployees joined the operations staff in November. The new Auxiliary Operators were participating in the Districts training progra=.

Special training was conducted by Co=bustion Engineering at Fort Calhoun Station on degraded core perfor=ance. Cycle T training is in progress.

No safety valve or PCRV challenges occurred.

A. PERF0FF.ANCE CHAPACTERISTICS 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 pa rformed in accordance with the annual surveillance test schedule. The following is a su==ar,r of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operation, Incidents Deficiency OI-lklk ST-ESF-7, D/LC-383-1 and D/LC-383-2 left and right F.3 level switches were out of setpoint tolerances.

OI-lh15 ST-ISI-CC-3 Missed 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> ISI signoff.

OI-lh20 ST-RM h, Environ = ental Air Sampler operational checks reading low flow.

OI-lh23 ST-FD-10, Not perfcrmed within the allovable time span of + 25%.

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Monthly Operations Report November 1981 Page Two C. RESULTS OF SUFEILLANCE TESTS AND INSPECTIONS (Continued)

Operations Incidents Deficiency OI-lh26 ST-ISI-CC-1 QC and Shift Supervisor not notified prior Component Cooling to start of test.

Water. #

D. CHANGES, TESTS AND EXPERI!EITS CARRIED OUT WITHCUT C0!C4ISSICN APEROVAL Procedure Descrintion SP-STRETCH-1 Power Ascension to 1500 myth.

The purpose of Special Procedure SP-STRETCH-1 was to provide a safe and orderly =ethod for initial power ascension to 1500 myth from the previously licensed power level. After having received the duly approved license amendment from the NRC to raise the Fort Calhoun rated power level from lh20 =vth to 1500 =vth, power was raised in a controlled manner per this Special Procedure.

The method used in raising pcver utilized existing plant procedures, guidance from Combustion Eng neer-ing, and guidelines from the Safety Analysis which was prepared to justify the power increase. Power was raised from lh20 cvth to 1500 =vth successfully and without incident.

This procedure did not involve an unreviewed safety l quest '.on per 10CFR50. 59 Power ascension was in accordance with Technical Specification requirements which were in turn justified to, and approved by, the Commission.

SP-FAUD-1 An unreviewed safety question as defined in 10CFR50 59 did not exist as this procedure only involves evaluat-ing data from a surveillance test.

E. RESULTS OF LEAK RATE TESTS l Annual Leak Bate Tests are in progress. A consolidated report will be

[ made at the end of testing.

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Monthly Operations Report November 1981 Page Three F. CHANGES IN PLANT OPERATING STAFF The following personnel vere promoted to the following positions and made effective December 1, 1981.

Merl R. Core - Supervisor - I&C and Electrical Field Maintenance.

Bruce J. Hickle - Supervisor -Chemistry and Radiation Protection.

Dick Hyde - Supervisor - Field Maintenance i Two new STA e=ployees joined the Technical staff in November.

Three new e=ployees joined the Operations staff in November.

G. TRAINING Training during the month of November consisted of General Enployee Training, Crane Operator Training, Hot License Training for NRC Examinations, Monitor Team and Emergency Duty Officer Training.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY

COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 NONE II. MAINTE'IANCE (Significant Safety Related) .

M.O. # Date Deecriration Corrective Action __

12326 10-20-81 RM-050 is spiring in alert. Balanced alarm board, 11723 9-29-81 Replaced RPS-D channel B-10 detector. Removed old detector and replaced per MP-PR-WRD-1.

11810 9-29-81 Replaced RPS-B channel B-10 detector. Removed old detector and replaced per MP-PR-WRD-1.

9353 10-30-81 Couple Control Element Assemblies Completed per procedure.

MP-RC-10-T.

12366 10-22-81 HCV-403A/C will not operate via the Installed new coil in solenoid control switch. valve.

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,V Approved By: . .

S.C.Stdvens Manager-Fort Calhoun Station