ML20070F046

Monthly Operating Rept for Nov 1982

ML20070F046
Person / Time
Site:	Fort Calhoun
Issue date:	12/10/1982
From:	Matthews T OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20070F033	List: ML20070F030 ML20070F046
References
NUDOCS 8212200064
Download: ML20070F046 (9)

Text

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AVJRAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 WIT Fort Calhoun Station DATE December 10, 1982 COMPLETED BY T. P. Matthews TELEPHONE (402)536-4733 MONTH November, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 301.8 376.3 37 2 303.4 376.1 18 3 306.0 39 376.3 4 305.4 376.0 20 5 304.8 374.7 21 6 306.3 374.9 22 7 306.7 '

374.8 23 8 306.5 375.7 24 9 308.5 378.4 25 39 307.8 278.5 26 316.9 378.6 27 12 344.0 379.5 28 13 369.0 379.5 29 34 374.9 3o 378.9 15 375.9 3, _

16 376.5 INSTRUCTIONS

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

(9/77) 821220006405000285 gDRADOCK 821213 PDR

OPERATING DATA REPORT DOCKET NO. 50-285 DATE December 10, 1982 COMPLETED BY -T. P. Matthews TELEPHONE (4021536-4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: November, lbfdZ

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 0

6. Maximum Dependable Capacity (Gross MWe): 5

7. Maximum Dependable Capacity (Net MWe):

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

None

9. Power Level To Which Restricted,if Any (Net MWe): N/A

10. Reasons For Restrictions. If Any: None This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 720.0 8,016.0 80,497.0

12. Number Of 11ours Reactor Was Critical 720.0 7,801.5 64,040 3

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 720.0 7,787.5 62,8//.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 788.152.6 10.832,932.7 77,534,762.8 .

17. Gross Electrical Fnergy Generated (MWH) 267,634 1 _. 3.633.373.9 25.707.319.5

18. Net Electrical Energy Generated (MWH) 251.817.1 3.455,732.6 24.303,601.1

19. Unit Service Factor 100.0 97.1 78.1

20. Unit Availability Factor 100.0 97.1 78.1

21. Unit Capacity Factor IUsing MDC Net) 73.2 90.2 65.6

22. Unit Capacity Factor (Using DER Net) 73.2 90.2 65.3

23. Unit Forced Outage Rate 0.0 2.9 3.8

24. Shutdowns1983 refueling Scheduledoutage Over Next 6 Months commenced December (Type.7, I Date, b

and Duration earlier than planned, of FaE8b:

! due to a forced outage resulting from turbine bearing and rotor blade problems.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 15, 1983

26. Units in Test Status (Prior to Commercial Operationi: N/A Forecast Achiesed

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50-285 -

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Fort Calhoun Station DATE December 10. 1982 November, 1982 COMPLETED BY T. P. Matthews REPORT MONTi{ TELEPflONE (402)536-4733

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, .! E 3 ) .E Licensee ,E r, e o Cause & Corrective No. Date g g 2; jg5 Event 37 o.1 Action to H jE $ e;

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u Present Recurrence 6

There were no unit shutdowns during the month of November, 1982.

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B4far.tenana of Test )- '2-Manual Scram. Entri Sheets fer Licensee .J C-Refuetag 6 3 Aatomatic Scrara. Eve.it Repn t (LER) File (NURPG ' ,

D. Regulatory Restriction j 4 Othe Cixplain) 0161) -

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\ Refueling Information Ebrt Calhoun - Unit No.1

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(Reportifor the nonth ending November 1982 .

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

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2'. T teduled date for restart following refueling. Nay, 1984

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f . 3. Mill refueling or resumption of operation thereafter f require a technical specification change or other

,i license amendment?

Yes s ,

~ _. ' s a If answr is yes, what, in general, will f .,

-these be?

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i A Technical Specification Change t .n i

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", b. If answer is no, has the reload fuel design ard core configuration buen reviewed by your Plant Safety Review Corrmittee to deter-mine whether any unreviewed safety questions are associated with thn core reload.

+ c. If no such review has taken place, when is y it s.teduled? -

i , 4. Scheduled date(s) for srhnitting proposed licensing 1 action and support infonnatiqn. February, 1984 s -

5. . Imoortant licentiing considei-Ations associated with g' N( refueling, e.g.,. new or,Giff9. rent fuel design or supolier, unreviewed de.si(gt or performance analysis

,,. , net. hods, significant cranges in fuel design, new 4 operating procedures. , ~

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6. The numoer of fuel assemblies: 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 l -

, storage capacity 728 f $ 7. The projected date of-the 'last refueling that can be l discharged to the spent fuel pool assuming the present licensed capacity.

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Mont,hly Operations Repord

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, I. OPERATIONS SU:4fARY > I,> >

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Fort Calhoun Station began increasing fpver Nover.ber 'll,,1982 from, ,' s 65", power while Nebraska City went off 811ne. ' The plant van . stabilized I

'at 78% power November 13, 1982 and remained. t that power level through

's the rest of the month. ,

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Four bundles of new fuel were received' November 3, fl982.

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}/ Annual licensed operator requaIffl. cation ' examinations are under way 6 i

and will be completed December 2,,1902.

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[' .. i No safety valve or PORV challenges occurred.  !

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• PEdFORMANCECHARAC,TERISTICS

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1 LER Number  ! 'I Deficiency

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B. CHANGES IN OPERATING METHODS liONE I

i C. RESULTS OF SURVEILL/HCE TESTS AND INSPECTIONS Surveillance tests..as required by the Technical Specifications Section 3.0 and Appendix B,' vere performed in accordance with j

i the anndal surveillance test schedule. The following is a summary of the curveillan'ce tests which resulted in Gperation i Incidents and are noti reported elsewhere in the report:

1 Operation Incidents Deficiency OI-1597 ST-SUTE"P-1 During performance of Surveillance Test, TIA-135 and TIA-136 indicators were erroneously logged.

OI-1601 ST-ESF-6 DG-1, governor booster pump motor was removed J

I and sent out for repair without maintenance order.

OI-1602 ST-DG-2, During performance of ST-DG-2, several switches l F.1, F.2, noticed to be out of calibration tolerance.

F.3 Speed Sensing Switch, jacket water pressure, i

lube oil high temperature alarm, fuel oil base tank level.

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Mcnthly 0parations Raport November, 1982 Page Two i

C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (Continued)

Operation Incidents Deficiency 0I-1606 ST-CEA-1, While performing test, it was discovered that F.6 Group 4 PPDIL & PDIL setpoints set a higher value then they were suppose to.

D. CHANGES, TESTS AND EXPERLMENTS CARRIED OUT WITHOUT COM4ISSION APPROVAL 3

Precedure Descri cion ST-FE-1 Visual inspection of spent fuel. Comoleted per

procedure.

l This procedure did not constitute an unreviewed safety question per 10CFR50 59 since any potential accidents have been evaluated in the FSAR section on "~Iinal Handling Accidents".

SP-SFS-1 Shipment of Spent Fuel in NL1-1/2 Cask. Completed per procedure. ..

This procedure did not constitute an unreviewed safety question per 10CFR50 59 since redundant rigging was used and a potential fuel handling accident has been analyzed in the FSAR.

SP-UF6-1 9-28-82 Uranium Hexafluoride Storage Cylinder External Visual Inspection. Completed per procedure.

Performance of this procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 Handling and storage of the UF6 is

in accordance with license SMC-lh20 and thus does not affect the statioe operating license.

The safety impact of UF6 release would be less l severe than that of other types of chemical t

releases which have already been evaluated.

j SP-UF6 -1 10 4-82 Uranium Hexafluoride Storage Cylinder External Visual Inspection. Completed per procedure.

Performance of this procedure did not sonstitute an unreviewed safety question as defined by 10CFR50 59 Handling and storage of the UF6 is in accordance with license SMC-lh20 and thus does not affect the station operating license.

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4 Monthly Operations Report November, 1982 3

Page Three a

D. CHANGES, TESTS AND EXPERLMENTS CARRIED OUT WITHOUT COMMISSION '

l APPROVAL

, Procedure Descrittion SP-UF6 -1 10-h-82 (Continued) i.

4 The safety impact of a UF6 release would be less severe than that of other types of chemical releases which have already been evaluated.

SP-UFg -2 9-23-82 Off-Loading of UF6 Cylinders. Completed per procedure.

Performance of this procedure did not constitute an an unreviewed safety question as defined by 4

10CFR50 59 Handling and storage of the UF6 is in accordance with license SMC-lh20 and thus does not affect the station operating license.

The safety impact of UF6 release would be less severe than that of other types of chemical 1 releases which have already been evaluated.

SP-UF6 -2 10-1-82 Off-Loading of UF6 Cylinders. Completed per procedure.

Performance of this procedure did not constitute an unreviewed safety question as defined by 10CFR50 59 Handling and storage of the UF6 is in accordance with license SMC-lh20 and thus does not affect the station operating license.

The safety impact of UF6 release vould be less severe than that of other types of chemiet.1 releases which have already been evaluated.

SP-NFR-1 Fuel Receipt Procedure. Completed per procedure.

Performance of SP-NFR-1 did not constitute an unreviewed safety question per 10CFR50.59 New fuel receipts were performed in strict accordance with the station operating license and applicable regulations. No possibility existed of a signifi-1 cant radiological release in the event of mishand-ling.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it  :

only involved evaluating data from a surveillance test.

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Monthly Operations Raport November, 1982 Page Four E. RESULTS OF LEAK RATE TESTS NONE R

F. CHANGES IN PIRIT OPERA *ING STAFF NONE 1

G. TRAINING 2

Training for November,1982:

Operators, NRC licensed personnel were administered an annual requalification exam.

Non-licensed operators were trained on systems, theory and procedures on an as needed basis.

All operators received lectures on Emergency Procedures, the newly installed H2 analyzer SER, and reactor theory.

, All plant personnel attended general, employee training refresher on a scheduled basis in preparation for the 1983 outage.

4 j Maintenance received training on systems as scheduled.

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

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Monthly Operations Raport Hovember, 1982 Page Five II. MAINTENANCE (Significant Safety Related)

M. O. # Date Description Corrective Action 16875 10-11-82 RM0/60 pump will not start breaker Removed motor ard replaced.

tripped free.

16877 10-20-82 Charging Pump, CH-1A packing cooling Completed per MP-CH-1-1.

tank overfills when pump is shutdown.

16913 10-25-82 HCV-2633 valve has no indication Valve replaced.

light.

16889 10-20-82 B/PIC-905 Sigma failed to reset. Removed, repaired and reinstall-ed sigma.

16797 10-28-82 Replace motor & brake on CRDM-17. Replaced rectifier.

16937 10-29-82 NI "A" vide range channel irratic Re-calibrated.

indication.

16936 10-29-82 NI "D" vide range channel B-10 Re-calibrated.

detector irratic indication.

16921 10-28-82 S/G Pressure sigma low pressure trip Replaced indicating light.

light blinks.

16961 10-28-82 ROD #23 vill not operate. Repaired NC contract in raise relay.

1T208 11-5-82 TIA-221 sigma appears to have failed. Replaced alarm circuit.

16990 11-22-82 RM-055A needs to be cleaned. Cleaned RM-055.

16935 10-28-82 RC-2B Steam Generator leak on hand- Machined gasket surface and hole. repaired.

16933 10-28-82 RC-2A Steam Generator south handhole Machined gasket surface and leaks. repaired.

1693h 10-2T-82 RC-2A Steam Generator handhole leaks. Machined gasket surface and repaired.

16798 10-27-82 RC-2B support rod broken. Repair per procedure.

w 2?. b W. G. Gates Plant Manager I