ML20080C877

Revised Monthly Operating Rept for Dec 1982

ML20080C877
Person / Time
Site:	Fort Calhoun
Issue date:	01/10/1983
From:	William Jones, Matthews J OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20080C870	List: ML20080C868 ML20080C874 ML20080C877 ML20080C881
References
LIC-83-011, LIC-83-11, NUDOCS 8308290355
Download: ML20080C877 (9)

Text

3 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 3.li Fort Calhoun Station DATE danuary 10. 1983 COMPLETED BY T. P. Matthews TELEPil0NE (402)536-4733 December, 1982 gg _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe Net) 378.1 ,7 0.0 l 2 377.8 18 0.0 3 _

345.5 39 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 0.0 22 7 0.0

• 0.0 23 g 0.0 0.0 24 9 0.0 25 0.0 to 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 34 0.0 3o 0.0 15 0.0 3 0.0 16 0.0 i

l INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting inonth. Compute to the nearest whole rnegawatt.

(9/77) 8308290355 830804 PDR R

ADOCK 05000295 PDR

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• t OPER ATING DATA REPORT DOCKET NO.

50-285 DATE January 10, 1983 COMPLETED BY T. P. Itatthews TELEPilONE Ian? MM-4733 OPFRATING STATUS

1. Unic Name:

Fort Calhoun Station Notes

2. Reporting Period:

DecemDer, 1982

3. Licensed Thennal Power IMWt p: 1500

4. Nameplate Rating IGross MWe): 501

5. Design Electrical Rating INet MWe): 470

6. Masimum Dependable Capacity (Gross MWe):

7. Masimum Dependable Capacity (Net MWe): 470

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

N/A

9. Power Level To %hich Restricted. lf Anv (Net MWe): _

N/A

10. Reasons For Restrictions.lf Any: None This Month Yr..to-Date Cumulative i1. Hours In Reporting Period 744.0 8,760.0 81,241.0

12. Number Of flours Reactor Was Critical 70.0 /,8/1.b e4,ilu.d

13. Reactor Resene Shutdown Hours 0.0 0.0 1,309.b

14. Ilours Generator On-Line 70.0 7,857.5 62,94/.5

15. Unit Resene Shutdown Houn 0.0 0.0 Uu

16. Gross Thermal Energy Generated (Mwil 81,785.6 10,914,718.3 77,616,548.4 .

17 Gross Electrical Er.ergy Generated IMWil) 28,014.0_ _ _, 3,661,387.9 25,/35,333.b

18. Net Electrical Energy Generated (MWilj 26,433.3 3,482,165.9 24,330,034.4

19. Unit Senice Factor 9.4 89.7 77.5

20. Unit Asailability Factor 9.4 89.7 77.5

21. Unit Capacity Factor (Using MDC Net) 7.4 83.2 65.0

22. Unit Capacity Factor (Using DER Net) 7.4 83.2 64.7

23. Unit Forced Outage Rate 49.3 3.6 3.9 of Fa

24. Shutdowns1983 Scheduled Oser Ne.st refueling outage 6 Monthsearly con #.enced (Tvpe.onDate.and 11uratioOecembh rer 6, 1982.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 20, 1983

26. Units lei Test Status (Prior to Commercial Operation): N/A Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY CO\l\tERCIA L OPER ATION (9/77)

50-285 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N Ah1E Fort Ealhnnn Station DATE Jantiary 10. 1983 COhlPI.E'IED llY T_ P Matthotm REPORT hlONTil December, 1982 (40215?6-471's TEl.EPilONE

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= e. 3 -2  : .

l.tcensee c Cause & Corrective

.2 _e E ,EX g t, No. Date g g g ,g g $ Event  ? 8%3 Action to

'E 0 ' Present Recurrence

$5 $ j5g Report #

b 82-05 821203 F 68 A 3 N/A HA TUP. BIN The reactor tripped on December 3, 1982 because of high turbine vibra-tion. Af ter investigation, it was determined that the first stage rotor of the H.P. turbine had broken blades and wiped bearings.

82-06 821206 S 606 C 4 N/A XX XXXXXX Subsequently, it was decided as of December 6,1982 to conmence the 1983 refueling outage approxi-mately one month early.

3 4 I 2 Reason: hiethod: Exhibit G - Instructions F: Forced for Preparation of Data S: Scheduled A Equipment Failure (Explain) 141anual 2 klanual Scram. 1:ntey Sheets for I.icemee li hlaintenance of Test C-Refuehng 3-Automatic Scram. Event Repost (i.liRilifeINURIG D. Regulatory Restriction 4 Other (Explain) 01611 E-Operator Training & l.icense Examination 5

F-Administrative G-Operational Error (Explain) Eshibii I - Same Source (9/77) Il-Other (Explain)

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. Refueling Information Fort Calhoun - Unit No. l Peport for the month ending December 1982

, 1. Scheduled date for next refueling shutdown. March 1984

2. Scheduled date for restart following refueling. May 1984  ;

3. Will refueling or rest =ption of operation thercafter require a technical specification change or other license amendment? Yes

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

A Technical Specification Change

b. If answ r is no, has the relcad fuel design ard core configuration been reviewd by your Plant Safety Review Cc~rtittee 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 Methodology - Dec. 1983 action and support information.. -

Tech. Specs. - Feb. 1984

5. L portant 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 cperating procedures.

6. The nutber of fuel asse:rblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool ,

storage capacity 483 d) planned spent fuel pool storage capacity 728

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 Prepared by / M#M Date January 4, 1983 i . /

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01U0U( PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 December, 1982 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station entered the month of December at 78% power.

On December 3,1982, the plant tripped off line due to high vi-bration of the turbine bearings. Upon investigation, the turbine was found to have lost six buckets of f the first stage high pres-sure rotor and wiped several of the bearing facings. It was then resolved to move up the scheduled dato of the maintenance / refueling outage.

Presently, the control rods have been uncoupled, the reactor coolant system is at the middle of the hot leg and steam generator eddy current testing has been completed.

In preparation for the full off load of the reactor core to the spent fuel pool, cutting up of used incore flux detectors for proper storage has been completed and the shuffle of spent fuel already in the pool has commenced for allotment of room.

Annual licensed operator requalification examinations were com-pleted by December 2, 1982.

No safety valve or.PORV challenges occurred.

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 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 OI 1615 ST-ES F-3, During the performance of ST-ESF-3, F. 2 F.2, pressure switches / sensors were found out of calibration, A/PC-742-2, B/PC-742-2, C/PC-742-2, D/742-2, A/PC-742-1, C/PC-742-1, D/PC-742-1

-_ - . -. . . = . _ - _ . - . .- .

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Monthly Operations Report December, 1982 Page Two C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (continued)

, Operation Incidents Deficiency 1

OI 1612 ST-MSSV-1 During the performance of ST-MSSV-1, F.1 F.1, valves MS-275, 278, 280 and 282 failed to actuate within tolerance ,

of setpoints.

1 01 1616 ST-RM-4 During performance of ST-RM-4, F.1, F.1 sampler OAA was found to be inoperable '

due to a blown fuse.

OI 1617 ST-FW-2 During performance of ST-FW-2, F.2, F.2 flow indicctors FI-1109/FI-1100 lo-i cated on AI-66A/B were found to be i

operating out of setpoint tolerance.

3 D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i

i Procedure Description SP-PORV-2 -

PORV Setpoints. Completed per procedure.

The performance of this procedure did not constitute an unreviewed safety question as defined in 10CFR 50.59 because it was performed using normal plant operating procedures ensuring the operability of redundant equipment during setpoint changes.

10/23/82 PORV Setpoints. Completed per procedure.

The performance of this procedure did not i constitute an unreviewed safety question as defined in 10CFR 50.59 because it was performend using normal plant operating procedures ensuring the operability of redundant equipment during setpoint changes.

10/27/82 PORV Setpoints. Completed per procedure.

The performance of this procedure did not

, constitute an unreviewed safety question as defined in 10CFR 50.59 because it was 4

performend using normal plant operating procedures ensuring the operability of redundant equipment during setpoint changes.

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,r r, _ . _ , ~ , -,,,--,,.r. _ , , _ , . . , . , _ _ - , , , . . - . . - . . , ..,-.,_.-,.,.v .,_g., ,,,,._,7 mm, , ..p.,.y..- - , . ,, r, -

Monthly Operations Report December, 1982 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COM-MISSION APPROVAL Procedure Description SP-IC-11 Disposal of Irradiated Incore De-tector. Completed per procedure.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the cutting and loading of incore detectors. Ap-propriate radiation protection procedures were followed.

E. RESULTS OF LEAK RATE TESTS Local leak rate tests conducted during refueling outages were performed during December. A summary report will be submitted as required by the Technical Specifications.

F. CHANGES IN PLANT OPERATING STAFF None.

G. TRAINING Training in December was directed at General Employee initial and refresher badge certification. Classes were included to handle the influx of personnel due to the forced outage in early December. Topics include security, tagging, procedural compliance, radiation protection, crane operator certification, hydrotesting and fire barriers.

H. CHANGES, TEST AND EXPERIMENTS REQUIRING NUCLEAR REGU-LATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59.

None.

Revised 8/24/83

Monthly Operations Report December, 1982 Page Four II. MAINTENANCE (Significant Safety Related)

M.O. # DATE DESCRIPTION CORRECTIVE ACTION 17298 11/16/82 RM-056 will not cal check properly. Replaced high alarm switch.

17408 12/3/82 AC-3B component cooling water Completed per MP-AC-3-1.

pump - inboard seal leaks.

17500 12/9/82 Raw water strainer will not run Cleaned and lubed breaker, electrically.

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$f/. 5 W. G. Cates Manager l Fort Calhoun Station

Omaha Public Power District '

g423 MANNEy e O M A N A. NEeRA5MA 6e102 e TELEPHONE S36 4000 AREA CODE 402 l January 10, 1983 1

LIC-83-011

!1r. Richard C. DeYoung Director Office of Inspection and Enforcement U. 5. fluclear Regulatory Comission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the December Monthly Operating Report for the Fort Calhoun Station Unit tio.1.

Sincerely, s

[N W. C.l; Jones Divis'. ion Manager Production Operations WCJ/TLP:jem Enclosures cc: NRC Pegional Office Office of !!anagement & Prcgram Analysis (2)

Mr. R. R. Mills - Combustion Engineering tir. T. F. Polk - Westinghouse Mr. L. A. Yandell - flRC Senior Resident Inspector fluclear Safety Analysis Center NRC File

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