ML20042A729

Monthly Operating Rept for Feb 1982

ML20042A729
Person / Time
Site:	Fort Calhoun
Issue date:	02/28/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20042A717	List: ML20042A716 ML20042A729
References
NUDOCS 8203230721
Download: ML20042A729 (11)

Text

AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO. 50-285 UNIT Fort Calhoun Unit #1 DATE March 12, 1982 COMPLETED BY R. W. Short TELEPHONE (402)S36-4543 MONTli February, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) g y w,.3,, ,

I 462.9 37 321.6 2 466.1 is 376.9 3 476.7 39 457.2 4 477.3 20 475.9 5 475.8 21 483.6 6 473.4 22 485.8 7 476.8 23 486.5 8

478.4 486.5 24 9 479.1 25 485.2 10 228.4 26 486.2 11 0.0 27 485.7 12 17.3 28 485.4 13 384.2 ,,

i4 435.7 3, is 452.7 3, 16 457.3 INSTRUCTIONS On this format. list the average daily unit power Icvelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

8203230721 820312 PDR ADOCK 05000285 R PDR

4 OPERATING DATA REPORT DOCKET NO. 50-285 DATE March 12, 1982 COMPLETED BY R. W. Short TELEPHONE (4021536-4543 OPER ATING STATUS

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

2. Reporting Period: Februa ry, 1982

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net M)/c): 470 bul

6. Masimum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe): 478 .,

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

None

9. Power Lese! To Which Restricted.If An 'et MWe):

N/A

10. Reasons For Restrictions. lf Any:

This Month Yr to.Date Cumulative II. Hours In Reporting Period 672.0 1.416.0 73,897.0

12. Number Of Ilours Reactor Was Critical 618.5 1,362.5 57,601.5

13. Reactor Resene Shutdown Hours 0.0 0.0 1,309.5

14. Ilours Generator On Line 613.0 1,357.0 56,447.0

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (MWH) 876,324.7 1,969,834.5 68,671,664.6 .

17. Gross Electrical Energy Generated (MWH) 297,153.9 668,441.9 22,742,38/.b

18. Net Electrical Energy Generated (MWH) 282,681.3 637,276.5 21,485,145.0

19. Unit Service Factor 91.2 95.8 76.4

20. Unit Asai! ability Factor 91.2 95.8 76.4

21. Unit Capacity Factor (Using MDC Neti 88.0 94.2 bd.4

22. Unit capacity Factor IUsing DER Net) 88.0 94.2 63.1

23. Unit Forced Outage Rate 8.8 4.2 3.9

24. Shutdowns Scheduled Over Ne.st 6 Months (Type. Date.and Duration of Eachl:

None

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

26. Units in Test Status IPrior to Commercial Operationi: None Forecast Achiesed INITI A L CRITICALITY INIIIA L ELECTRICITY COMMERCI AL OPERATION (9/77)

DOCKET NO.

0-285 -

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Fort Calhoun #1 DATE March 12. 1982 COMPLETED BY R. W. Short REPORT MONTil February, 1982 TELEPilONE (4021536-4543 n.

5? 3 $ Licensee E t,  % Cause & Corrective No. Date h 3g i jg5 Event u' c'? Action to

$= 5 jgg Report ar SV ' Present Recurrence d

I 82-01 820210 F 50.0 A 1 82-005 RB CONROD Control rod inserted into the core due to a faulty magnetic clutch.

Replaced magnetic clutch.

82-02 820217 F 9.0 A 3 N/A NA INSTRU-C A circuit card in the electro-hydraulic turbine control system malfunctioned. Replaced faulty circuit card.

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 Repor (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G Operational Error (Explain) Eshibit I - Same Source (9/77) Il-Other (Explain)

Refueling Information Ibrt Calhoun - Unit Ib.1 Peport for the trenth ending February 1982 ,

1. Scheduled date for next refueling shutdown. Janu'ary 7, 1983

2. Scheduled date for restart following refueling. April 1, 1983

3. Will refueling or resunption of operation thereafter require a technical specification change or other license am2ndment? Yes

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

A Technical Specification change.

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Conmittee 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 action and support infonration. October 1. 1982

5. Inportant 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 l operating procedures.

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6. The number of fuel assemblies

a) in the core 133 asscanblics

! b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool "

storage capacity 483 l

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 Date March 1. 1982

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit-No. 1 February, 1982

Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station maintained a nominal 100% power during February with the following exceptions:

(1) February 10, 1982 / CEDM #2h clutch failed causing a control rod to 2

drop into the core. A controlled power reduction was initiated.

I The unit was returned to ' service February 12, 1982.

(2) February 17, 1982 a malfunction of the turbine control valves caused a automatic reactor shutdown. The unit was returned to service early on February 18, 1982.

A unusual event was declared on February 3, 1982 due to a radioactive gas leak from the auxiliary building vent header. Conditions ~ returned to j normal the same day and no Technical Specifications release limits were

, exceeded.

One additional reactor operator's license was received during February.

The operations staff completed the annual radiation / security refresher i

during February.

I-No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS l

LER Number' Deficiency LER 82-01 During normal operation, while performing ST-FP-9(F.1),

two fire barrier penetrations were found to be non-functional. The Shift Supervisor was immediately

notified. Contrary to the requirements of Tech. Spec.

2.19(7), a fire watch was not posted'within one-hour, nor was an hourly fire watch patrol established. The fire detector zones adjacent to the degraded fire bar-riers were operable.

LER 82-02 During power operations at approximately 99% power, lockout relay 86B1/CRHS (Containment Radiation High Signal) failed to actuate on demand by the plant radiation monitoring system. This resulted in the failure of one of the Engineered Safety Feature Channels to operate. However, during the incident all redundant CRHS lockout relays (86A/CRHS, 86A1/CRHS and 86B/CRHS) functioned as designed and initiated appro-pric+e safeguards equipment as required.

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Monthly Operations Report February, 1982 Page Two B. CHANGES IN OPERATING METHODS NONE C. RESULTS OF SURVEILI.ANCE 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 summa g of the surveillance tests which results in Operation Incidents and are not reported elsewhere in the report:

Operation Incidents Deficiency OI-1496 ST-DG-2 Diesel Generator #2 devices, out of tolerance.

Fuel Oil Transfer Pump #2 low pressure alarm,.

Fuel Oil Transfer Pump #2 high pressure alarm,.

local tachometer, lube oil pressure idle pres-sure lov. alarm & engine trip.

OI-1500 ST-ESF-1k ~ Not completed on time. Engineered Safeguards.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-STRETCH-2 The purpose of Special Procedure SP-STRETCH-2 was to measure and compare dose rates in various areas at 1500 MWth with dose rates at 1420 MWth. This

( test was performed following licensing approval to measure reactor power from lh20 to 1500 MW.

This procedure did not involve an unreviewed safety question per- 10CFR50.59 since plant operation was-totally unaffected. The test consisted entirely of measuring dose rates at various locations.

SP-FAUD-1 2-4-82 / Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50 59 since it l only involved evaluating data from a surveillance test.

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Monthly Operations Report February, 1982 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSTION APPROVAL (Continued)

Procedure Description SP-FAUD-1 2-5-82 / Fuel Assembly Uplift Condition Detection.

This procedure did not ecmtitute an unreviewed safety question as defined by 10CFR50 59 since it only involved evaluating data from a surveillance test.

SP-FAUD-1 2-6-82 / 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.

, SP-FAUD-1 2-8-82 / 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.

SP-FAUD-1 2:94i27/ 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.

l SP-FAUD-1 2-10-82 / Fuel Assembly Uplift Condition Detection.

l This procedure did not constitute an unreviewed j safety question as defined by 10CFR50.59 since it l only- involved evaluating data from a surveillance i test.

l SP-FAUD-1 2-11-82 / 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 Report February, 1982 Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description SP-FAUD-1 2-12-82 / Fuel Ass'embly 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.

SP-FAUD-1 2-16-82 / 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.

SP-FAUD-1 2-17-82"/ 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. -

SF-FAUN 1 2-18-82 / 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.

SP-FAUD-1. 2-19-82 / 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 t est..

E. RESULTS OF LEAK RATE TESTS NONE

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Monthly Operations Report February, 1982 Page Five F. CHANGES IN PLANT OPERATING STAFF Effective March 1, the following people will be appointed tJ the designated areas.

Fred Smith - Plant Chemist Gary Roach - Plant Health Physics G. TRAINING Training for the month of February included General Employee Training in Security, Radiation Protection,.First Aid and Driver's Training.

Systems Training was held for Maintenance. Operators Requalification Training continued as scheduled.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59 Amendment No. 6h revised the reactor coolant system pressure-temperature lirits for operation through 6.1 effective full power years.

t W.

S.-C. Steve (s Manager Fort Calhoun Station 4

e Monthly Operations Report February, 1982 Page Six II. MAINTENANCE (Significant Safety Related)

M. O. # Date Description Corrective Action 13020 12-6-81 AC-33h leaks. Replaced bonnet gasket and repacked valve.

13450 12-23-81 CH-181 has flange leak. Lapped disc and seat.

12530 1-27-82 480V Load Shed lockout switches did Tested.

not operate properly.

13020 12-6-81 AC-334 leaks. Removed bonnet, cleaned inter-nals & seat repacked.

13h50 12-23-81 CH-181 flange leak.. Lapped dise & seat, j 12530 11-27-81 OPLS 480V Load Shed. Checked circuitry.

12142 11-27-81 Excessive ripple on power supply for Found ground & cs?.ibrated.-

power supply for D-122C.

13549 1-h-82 NP-4 Circuit #21-tripped & will not Replaced NP-2 #2.

reset.

13711 1-21-82 FCV-U 01 valve-flow spiked low & Found loose terminals and returned, repaired.

13126 12-7-81 CH-396 suction relief on B Boric Replaced gaskets.

Acid. Tank leaked 125h7 1-25-82 HCV-306 stroke time slow. Solenoid valve replaced _

10468 1-24-82 HCV-2968 valve leaks. Repaired per procedure.

12977 12-3-81 HCV-402B will not open from control Replaced solenoid valve.

! switch.

n8h3 12-6-81 HCV-509A,B leaking through. Installed new diaphrams and leak tested.

j 13h28 12-23-81 LCV- nT3 leaked through. Lapped seat & face..

128hh 11-20-81 FM-212 reads low. Replaced square root extractor.

n905 10-20-81 RC-319 packing leaks. Replaced valve.

9823 12-3-81 HCV-335 valve leaks around flange Replaced gaskets-gaskets.

. 13275 12-14-81 PCV-103-2 repair or replace valve Replaced ac*untor.

operator.

f Monthly Operations Report February, 1982 Page Seven II. MAINTENANCE (Significant Safety Related)

M. O. # Date Description Corrective Action 4

13264 12-16-81 TI-A/122H Reactor Coolant Loop Z Replaced butt splices on con-pegged lov. tair. ment side of electrical penetration.

1 99h3 12 4-81 Component Cooling Water from VA-8A Blown fuse in power supply, no flow alarm.

12642 12 h-82 Containment Cooling Flow Ind. VA-8B Bad connection in amplifier pegged high. board.

, 11426 9-18-81 CH-1B leaking through primary Maintenance performed per packing. MP-CH-1.

13276 12-16-81 A-112H Reading high. Replaced butt splices on con-tainment side of electrical penetration.

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