ML20054G773

Monthly Operating Rept for May 1982

ML20054G773
Person / Time
Site:	Fort Calhoun
Issue date:	06/08/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20054G770	List: ML20054G769 ML20054G773
References
NUDOCS 8206220287
Download: ML20054G773 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE June 8,1982 COMPLETED BY R. W. Short TELEPHONE (h02) 536-4543 N, 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(Mwe.Neu i

h82.5 h77.3 37 2

481 9 18 h76.6 3

h 80. h 19 h7h.3 477.3 20 473.7 4

478.h 5

21 472.2 480.0 22 h78.2 6

h81 1 h80.6 7

23 480 3 8

24 479.7 9

h78.6 h78.2 25 to h77.8 h78.2 26 II h 7h. 0 27 477 1 470.4 h76.4 12 28 h73.7 1 76.8 i3 9

6 1677. 0 h75.9 14 30 15 k79 9 3

h78.5 kIO 1 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe. Net for each day in the reporting inonth. Coinpute ta the nearest whole negawatt.

(9/77) 8206220287 820610 PDR ADOCK 05000285 R

PDR

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE June 0,1982 COMPLETED BY.

B. W.

Short TELEPHONE (h02) 536-h5 h3 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes r

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2. Reporting Period:

May, 1982

3. Licensed Thermal Power (MWt): 1900

4. Nameplate Rating (Cross \\lwe): 501 S. Design Electrical Rating (Net MWe): h78

6. Maximum Dependable Capacity (Gross MWe): 501

7. Maximum Dependable Capacity (Net MWe):

h78

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

Mone

9. Power Lesel To Which Restricted. lf Any(Net MWe):

N/A

10. Reasons For Restrictions. If Any:

N/A This Month Yr..to Date Cumulative

11. Ilours in Reporting Period 7hh.0 3623.0 76,10h.0

12. Number Of flours Reactor Was Critical 744.0 3556.9 59,795 9

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.5

14. Hours Generator On-Line 7hh.0 35h7.8 58,637.8

15. Unit Resene Shutdown Hours 0.0 0.0 o,o

16. Gross Thermal Energy Generated (MWil) 1,108,564.2 5.210.667.h 71.912.497.5 17 Grow Electrical Energy Generated (MWil) 371,854.0 _. 1.767,013.9 23,840,959.5 i

18. Net Electrical Energy Generated (MWil)

_955.725.1 1,685,909.1 22,533,777.6

19. Unit Service Factor 100.0 97.9 77.0

20. Unit Availability Factor 100.0 97,9 77,o

21. Unit Capacity Factor IUsing MDC Net) 99.9 97.4 64.5

22. Unit Capacity Factor IUsing DER Net) 40.0 97.4 64.1

23. Unit Forced Outage Rate 0.0 2.1

3. 8

24. Shutdowns Scheduled Oser Next 6 Months IType.Date.and Duration of Eacht:

None

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

N/A

26. Units in Test StatusiPrior to Commercial Operations: None Forecast Achiesed INillT L CRITICA LII Y INITIA L ELECTRICI TY l

CO\\lM ERCI A L OPER A TION i

I (9/77)

DOCKET NO.

50-285 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT N AME Fort Calhoun Station DATE J une 6, 1902 COMPLETED HY ' R. W.

Sh ort REPORT MON Til MW. 108?

TELEPIIONE (h02) 536 h5h3 e.

E 5

j?

3 4 $2 Licensee

,E t, jg Cause & Corrective No-Date i

3i s

is5 Event gy g3 Action to f5 5

jgg Report a mO L

Present Recurrence H

g 6

There were no unit shutdowns or power reductions during the month o f May, 1982.

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4 F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Pseparation of Data B. Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (1.E R) File (NUREG-D Regulatory Restriction 4-Ot her (I!xplain) 0161) li-Operator Training & License Examination F Administrative 5

G-Operational Error (Explain)

Exhibis 1 - Same Source (9/77)

II Other liixplain)

Refueling Information Fort Calhoun - Unit No.1 Report for the tronth ending May 1982 1.

Scheduled date for next refueling shutdown.

January 3. :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 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 Comittee 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.

November 1, 1982 5.

Inportant 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 operating procedures.

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6.

The number of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool i

storage capacity 4na d) planned spent fuel pool 728 a

storage capacity 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 M

Date June 2, 1982 g

e

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

OPERATIONS

SUMMARY

Fort Calhoun operated at a nominal 100% power during May. No planned or forced outages occurred during May.

Extensive training for the operations staff in the area of Pressurized Thermal Shock was conducted during May.

The Supervisor - Operations participated in an advisory committee on Reactor Safeguards hearing on Pressurized Thermal Shock in Washington, D.C.

A special audit was conducted by NRC in the areas of Surveillance Tests, Maintenance, and Storeroom facilities with no outstanding violations or deviations identified.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS LER Uumber Deficiency LER-82-002 During power operations at approximately 99% power, (Revision 1)

Stack Particulate Process Radiation Monitor RM-061 tripped causing a CRHS (Containment Radiation High Signal) actuation due to the vaste evaporator being opened for inspection and the existence of a temper-ature inversion. After CRHS actuation, it was noted that lockout relay 86Bl/CRHS had failed to trip.

This resulted in the failure of one of the Engineered Safety Feature channels to operate. However, during the incident all redundant CRHS lockout relays (86A1/

CRHS and 86B/CRHS) functioned as designed and initiated appropriate safeguards equipment as required.

LER-82-008 During performance of ST-FW-1, F.2(b)(6) per Technical Specification 3.9, an attempt was made to start FW-10 (steam driven auxiliary feedvater pump).

The steam valves opened but the pump did not start.

The electric motor driven auxiliary feedvater pump was operable at the time of occurrence to mitigate any loss of feedvater accident that could have occurred.

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Monthly Operations Report May, 1982 Page Two A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency LER-009 During normal power operation, in the process of_

exchanging component cooling water heat exchangers, the associated outlet valves HCV 490B, HCV-h913 and HCV h 2B did not open.

(HCV-491B opened partially.)

9 The consequence of this event was that only one com-ponent cooling vater heat exchanger was operational.

Tech. Spec. 2.3(1)g requires three of four CCW heat exchangers to be operable which may be modified to two of four component cooling heat exchangers operable for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under Tech. Spec. 2.3(2)c.

B.

CHANGES IN OPERATING METHODS NONE C.

RESULTSOFSURVEILLANCETESTSANDINSPECTI$NS 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 i

OI-1536 SIS-ISI-SI-l Test not reviewed within 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> signoff time.

t 01-1537 ST-DC-1 During performance of ST-DC-1, test cells 35 & 36 of Battery #1 and cells 25, 39, 4), 45, 46, 47, 53, 54, 55, 56 & 59 of Battery #2 vere found out of tolerance.

01-1538 ST-RPS-1, V0PT reset switch would not recet.

(Power F.3 Range Safety Chanacls Test).

01-1539 ST-PL-1, LC-101-Y failed to start the backup Cooling F.2 Pump.

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Monthly Operations Report May, 1982 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT C0!C4ISSION APPROVAL Procedure Description SP-PRCPT-1 Post Refueling Physics Testing & Power Ascension:

This procedure did not constitute an unreviewed safety question per 10CFR50 59 All testing and Operations were performed in accordance with rou-tine plant operating procedures and station Tech-nical Specifications.

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.

E.

RESULTS OF LEAK RATE TESTS NONE F.

CHANGES IN PLANT OPERATING STAFF W. G. Gates was named Manager-Fort Calhoun Station effective May 16, 1982.

G.

TRAINING Training for the month of May.

Operations-Requalification Program continued as scheduled.

Technical Services provided training in Pressurized Thermal Shock and Water Treatment.

New licensed training was conducted on an individual basis.

Fire Brigade training for Operations and Guards were conducted.

Maintenance - training on the following topics was held:

Procedures, Monitor Teams, Primary Sampling and the Monthly Safety Meeting.

H.

CHMIGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY CO c4ISSION AUTHORIZATION PURSUANT TO 10CFR50 59 NONE

Monthly Operations Report l

May, 1982' l

Page Four l

II.

MAINTENANCE (Significant Safety -Related) 4 M. O. #

Date Description Corrective Action i

11565 9-18-81 Receiving intermitting hi power & APD Replaced 18 volt power supply.

i pretrip & trips on "C" RPS Channel.

Verified performance by_Sury..

Test.

Ih342 3-23-82 HCV-506A vill not move from the open Clean'ed solenoid valve on HCV-position and HCV-506B vill not appear.

506A. HCV-506B verified to be f

to go fully shut.

fully operable.

b 14581 h-12-82 Leak between CH-362 and CH-1A.

Weld repaired.

1h580 h-11-82 Valve is bound internally.

Loosened packing.

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f 1h207 3-7-82 Outboard seal. leaks when "B" CCW Replaced seal.

pump is riuming.

14632 h-15-82 Charging CH-1A appears to have' Replaced valve and rebuilt pump.

ingested a valve, flow is lov and amps oscillate.

s 14686 5-6-82 Waste Disposal valve WD-174 has a Replaced diaphram.

hole in diaphram.

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1h878 5-11-82 RPS "A" V0PT would not reset.

Replaced CB h switch.

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1463h 5-23-82 HCV 490A vill not open from control Valve mechanically hung up.

j switch on CB-1.

Freed up and repaired manual operator case.

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AU. h W. G. Gates Manager Fort Calhoun Station i

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