ML20054C381

Monthly Operating Rept for Mar 1982

ML20054C381
Person / Time
Site:	Fort Calhoun
Issue date:	04/12/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20054C380	List: ML20054C379 ML20054C381
References
NUDOCS 8204200473
Download: ML20054C381 (8)

Text

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t AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE Aoril 12. 1982 COMPLETED BY R IL Short TELEPHONE (402) 536-4543 MONTH March 1982 .

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe Neti I 485.3 37 485.4 2 485.1 18 484.9 3 485.2 39 481.2 4 484.7 20 459.0 5 484.3 21 457.4 6

484.1 g 456.4 7 484.0 23 456.0 8 484.8 y 456.0 9 486.2 25 455.3 10 485.8 26 454.7 Ii 485.5 37 471.4 12 485.4 3 482.9 l

i3 485.6 29 487.0 34 485.6 30 485.6 15 485.5 3, 485.5 l

16 485.6 INSTRUCTIONS On this format.hst the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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(9/77) 8204200473 820415 DR ADOCK 05000285 PDR ,

t OPERATING DATA REPORT DOCKET NO. 50-285 DATE Anril 12. 1982 COMPLETED BY R. W. Sh6rt TELEPIIONE f402) 536-4543 OPERA TING STAT US Fort Calhoun Station Unit No.1 Notes

l. Unit Name:

2. Reporting Period: March 1982

3. Licensed Thennal Power (MWtJ: 1600

4. Nameplate Rating (Grms MWe): 501

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross MWe): R01

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 Level To Which Restricted. lf Any (Net MWe): N/A

10. Reasons For Restrictions. lf Any: N/A This Month Yr. to.Date Cumulative i1. Ilours In Reporting Period 744.0 2,160.0 74,641.0

12. Number Of flours Reactor Was Critical 744.0 2,106.5 58,345.5

13. Reactor Reserve Shutdown flour, 0.0 0.0 ~

1,309.5

14. Ilours Generator On-Line 744.0 2,101.0 577191.0

15. Unit Rewne Shutdown lloun 0.0 0.0 0.0

16. Grms Thermal Energy Generated (MWil) 1,091,851.0 3,061,685.5 69,763,515.6

17. Grms Electrical Energy Generated (MWil) 372,710,0 _, 1.041,151.9 23,115,097.5 l 18. Net Electrical Energy Generated (MWil) 355,686.7 992,963.2 21,840,831.7

, 19. Unit Senice Factor 100.0 97.3 76.6 l 20. Unit Availability Factor 100.0 97.3 76.6 f 21. Unit Capacity Factor iUsing MDC Net) 100.0 96.2 63.8 l 22. Unit Capacity Factor (Using DER Nett 100.0 96.2 63.4 l 23. Unit Forced Outage Rate 0.0 2.7 3.9 l 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date,and Duration of Eacht:

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

26. Units in Test Status tPrior to Commercial Operationi: NONE Forecast Achiesed INIII A L CHI TICAl_li Y INI TI A L El.EC TRICITY COM\ll:RCI A L OPER AllON (9/77) l

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DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT N AME DATE Anril 17: 14R2 COMPLETED BY R- W. Short REPORT MONTil March 1982 TELEPilONE f407) M6 4543

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_ E E jg 3 4 Ei Licensee Eg je. Cause & Correctise No. Date i 3 4 is5 Event 33 g?U Action to W

f $ jg Report c mV g Prevent Recurrence 6

No unit shutdowns or power reductions during March 1982 I

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

E-Operator Training & License Examination F-Administrative 5 G Operational Error (Explain) Exhibit 1 Same Sourec (9/77) Il-Ot her (Explain)

l Refueling Information Fort Calhoun - Unit No. 1 Report for the nonth ending March 1982 .

l. Scheduled date for next refueling shutdown. January 7, 1983

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

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

a. If answer is yes, what, in general, will i 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 information. October 1, 1982

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or j supplier, unreviewed design or performance analysis

methods, significant changes in fuel design, new operating procedures.

6. The number of fuel assemblies: a) in the core 133 assemblies i "

b) in the spent fuel pool 237 -

c) spent fuel pool storage capacity 483 d) planned spent fuel pool i

storage capacity 483 l

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 Prepared by ) V Date April 1, 1982 U

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 March, 1982 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power during March with the exception of the period between March 19 and 26. During this period, power was reduced to a nominal 94% to maintain the phase angle between the 161 KV and 3h5 KV systems less than 100 in order to perserve the plant's fast transfer capability.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency LER-003 During routine operations at approximately 99% power, the containment isolation valve associated with the " gas vent header", (HCV-507A), failed to close upon demand. Dmer-gency Procedure, EP-25, " Loss of containment Integrity",

was immediately issued and followed. An emergency Main-tenance Order (M.O.) was written to correct the problem and the valve was restored to an operable status within the six hour time constraint of Technical Specification 2.0.l(1). During the incident, the redundant isolation valve, (HCV-50TB), remained operable and closed upon demand.

LER-00h During routine power operation at approximately 99% power, a small quantity of radioactive gas / particulate was released to the auxiliary building. This occurred while attempting to draw a sample of gas from the pressurizer steam space.

During the incident the stack gas monitor, RM-062, failed to alarm at the appropriate setpoint. RM-061, the stack particulate monitor did actuate at the desired setpoint and initiated a VIAS (Ventilation Isolation Actuation Signal).

The release of radioactivity to the atmosphere was of short duration and was within Tech. Spec. limits.

LER-005 While operating at 98% power, control element 24 inserted fully into the core. Emergency Procedure EP-13, CEDM Mal-functions", was implecented and power stabilized at 88%.

The event occurred at 0938 and the operator storted reduc-ing power at 0939 Technical Specification 2. 2(h)e requires power to be < 70% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the CEA drop.

Peactor power was stabilized at < 70" 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and h minutes following the CEA drop. The power reduction resulted in no adverse effects on fuel performance or integrity.

Monthly Operations Report March, 1982 Page Two

3. 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 results in Operation Incidents and are not reported elsewhere in the report:

Operation Incidents Deficiency OI-1503 S T-D G-1, During performance of this test the following F.1 & 2 instruments were out of calibration. DG-1, Engine Jacket Water Temp. Low Switch, DG-1, Fuel Oil Transfer Pump #2, Lov Pressure Alarm.

DG-1, Fuel Oil Filter #2, Inlet Pressure High Alarm. All out-of-specification instruments were L mediately recalibrated, retested, and found to be operating satisfactorily. In addition, EEAR FC-82-17 has been submitted to determine if the Diesel Generator instrumenta-tion should be upgraded.

OI-1506 S T-RM-2 , Ratemeter RM-062 was found to have a faulty F.2 Switch-high alarm. The high alarm switch was replaced per M.O. #1hl81 and the monitor satisfactorily passed the operability test per ST-RM-2, F.2.

OI-1509 ST-FP-10, Cable Spread Room Halon System. Manual actua-F.2 tion didn't giva ventilation isolation. EEAR l FC-82-33 has been initated to provide the modi-fications required to result in ventilation isolation upon manual initiation of the Cable Spread Room Halon System.

D. CHANGES, TESTS AND EXPERIME'ITS CARRIED OUT WITHOUT COMMISSION APPROVAL 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.

'o Monthly Operations Report March, 1982 Page Three E. RESULTS OF LEAK RATE TESTS NONE F. CHANGES IN PLANT OPERATING STAFF NONE G. TRAINING The R0/SRO Requalification Training progressed on schedule and included training in Systems, Thermodynamics, Fire Brigade Emer-gency Plan, and Reactor Theory. Maintenance Training on Systems and Procedures was conducted.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY CO?oIISSION AUTHORIZATION PURSUANT TO 10CFR50.59 NONE i'

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S .'i C. Stevens Manager Fort Calhoun Station l

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Monthly Operations Report ,

March, 1982 Page Four II. MAINTE MAINTENANCE (Significant Safety Related)

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II.

M. O. # Date Description Corrective Action 1h105 2-26-82 Secondary Air Start Pressure Regula- Rebuilt primary & secondary tor D-2. regulators. ,

lh2h3 3-10-82 RM-057 won't run. Replaced. motor bearings.

Ih101 2-27-82 Charging Pump CH-1C packing leak. Overhauled & installed new-packing. -

8188 2-18-82 RPS Temperature Loop B-TT/122H Loop Installed' Heat Shrink Tubing on Oscillating. shield drain wires.

13876 2-11-82' DG-2 Govenor is leaking oil. Replace govenor. ~

13936 2-10-82 TAR-3 Heat Tracing recorder Replaced 2h' volt transformer, '

inoperable. bridge, thyrector.

13884 2-5-82 Drive String broke on TAR-2. Heat Replaced broken string.

Tracing Recorder.

13927 2-16-82 Heat Tracing Recorder TAR-3 hung up. Installed new gear.

Ih016 2-17-82 Perform rod drop computer program for Completed.

CEDM #17 12837 12-6-81 Fitting between HCV-260hA & penetra- Tested & found no leaks.

tion M-23 damaged and will not seal.

12302 11-25-81 Inspect Reactor Coolant Pump RC-3A, Completed, no leakage.

B, C, D studs.

13795 2-1-82 Metrascope malfunctioning. Replaced power supply.

14000 2-16-82 CVCS Bi-Stables trip. Readjusted CP-101X & rerun test.

1382h 2-11-82 SI-222 relief to vent header is leak- Repaired.

ing by.

12853 11-28-81 HCV h02A, Component Cooling Water Replaced solenoid.

inlet to VA-TA cooler would not close.

1h01h 2-18-82 CV-1, 2, 3, h began to close result- Replaced oscillator card B09 ing in load rejection, lh092 2-25-82 Heat Tracing Recorder, TAR-2 print Complete.

lead needs readjustment.

13826 2-17-82 FCV-1101, Feedvater Regulating Valve Replaced proportional amplifier.

automatic controller started shutting valve.

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