ML20027E788

Monthly Operating Rept for Oct 1982

ML20027E788
Person / Time
Site:	Fort Calhoun
Issue date:	11/03/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20027E787	List: ML20027E786 ML20027E788
References
NUDOCS 8211160173
Download: ML20027E788 (8)

Text

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O AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

UNIT Fnet Calhnun Station DATE November 3, 1982 COMPLETED BY ' R W 9hnet TELEPilONE (anM 8;ma'i43 October 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe Neti I

404.5 37 308.8 406.5 309.5 2

18 3

406.5 309.6 i,

4 406.6 306.0 20 5

405.8 308.0 21 6

402.7 299.2 22 318.8 7.1 7

23 307.7 0.0 8

24 9

307.3 0.0 25 to 307.0 26 0.0 i

308.0 0.0 27 308.7 0.0 12 28 309.3 5.8 13 29 309.2 302.5 i4 3g 308.5 314.0 I5 3,

16 308.2 INSTRUCTIONS 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) 8211160173 821109 PDR ADOCK 05000285 R

PDR

OPERATING DATA REPORT DOCKET NO. 50-285 DATE Mnvomhar_3, 1982 COMPLETED BY R_ IL ShDrt TELEPHONE (402) W -4543 OPER ATING STATUS

^

1. Unit Name:

Fnet Falhnnn statinn Notes

2. Reporting Period:

October 1982

3. Licensed Thermal Power (MWt):

1500

4. Nameplate Rating (Gross MWe):

501

5. Design Electrical Rating (Net MWe):

47R

6. Maximum Dependable Capacity (Gross MWe): 501

7. Maximum Dependable Capacity (Net MWe):

478

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

None

9. Power LevelTo which Restricted.If Any(Net MWe):

N/A

10. Reasons For Restrictions.If Any:

None l

This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 745.0 7,296.0 79,777.0

12. Number Of Hours Reactor W s Critical 596.6 7,081.5 63,320.5

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Hours Generator On Line fi91.7 7,067.5 62,157.5

15. Unit Reserse Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 616.136.8 10,044 7,80.1 76.746.610.2

_ _2

17. Gross Electrical Energy Generated IMWH) 206,834.0_ _, 3,365,739.9 25.439.685.5

18. Net Electrical Energy Generated (MWH) 193.573.5 3,203,915.5 24,051,784.0

19. Unit Service Factor 79.4 96.9 77.9_

2o. Unit Availability Factor 79.4 96.9 77,9

21. Unit Capacity Factor (Using MDC Net) 54.4 91.9 65.5

22. Unit Capacity Factor (Using DER Net) 54.4 91.9 65.2

23. Unit Forced Outage Rate 20.6 3.1 3.8

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each t:

1983 refueling outage scheduled to commence January 3, 1983 for three months.

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

N/A

26. Units in Test Status iPrior to Commercial Operation):

None Forecast Achiesed INITIA L CRITICALITY INITI A L ELECTRICITY COMMERCIAL OPER ATION (4/77) t

~

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCLET NO-50-285 UNIT NAME Fort Calhnun 9tation DATE. Mauamher 1, 1082 COMPLETED BY R-W.

Shnet REPORT MONTH October 1982 TELEPHONE fan?) G16_aSa3

~.

3E 3

.I' Licensee E t, e,

Cause & Correctise No.

Date i

3g 5

,;i55 Event g?

g3 Action to 5

j ;ji g Report a mo g'

Prevent Recurrence H

5 82-04 821023 F

153.3 F

1 N/A HB xxxxxx Leakage from the secondary side of Steam Generator RC-2A was at a rate to warrant shutting down tne plant and effect repairs. The leakage was determined to have originated from three instrumentation handhole gaskets and several root valves.

These components of RC-2A were repaired to eliminate the leakage.

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 Report (LERI File (NUREG-D-Regulatory Rest'riction 4-Other (Explain) 01611 E-Operator Training & License Examinati n F-Administ rative 5

G-Operational Error (Explain)

Exhibit I - Same Source (9/77)

Il-Other (Explain)

Pefueling Information Ebrt Calhoun - Unit No.1 Report for the conth ending October 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 Cmmittee 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 infouration.

November, 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.

6.

The number of fuel assenblies: a) in the core 133 asserrblies 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 assu:ning the present licensed capacity.

1985 y,.

h M,( M Prepared by A

Date November 1. 1989

-/

~

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

OPERATIONS

SUMMARY

Fort Calhoun Station reduced power October 6 and 7,1982 from 85% to 65% for fuel conservation in order to meet the January 3,1983 refueling schedule. On October 23, 1982, the plant was taken off line for unschedul-ed maintenance. While in cold shutdown, three handholes and several root valves on the secondary side of the steam generator were repaired due to excessive leakage. The plant was back on line October 29 and resumed 65%

power October 30, 1982.

Annual licensed operator requalification training at Combustion Engi-neering simulator in Windsor, Connecticut was completed October 8,1982.

Arrival of uranium hexaflouride (UF ) was completed October 5,1982.

6 In all, 52 cannisters are stored on site.

The spent fuel shipping cask with spent fuel pins was shipped offsite October 1, 1982. These fuel pins are for DOE analysis of high burnup fuel.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency LER-017 During pre-operational testing of the redundant containment hydrogren monitors, a control room operator noticed that there was no valve position indication for in-board containment isolation valves, HCV-820B and 8218, associated with hydro-l gen moni tor VA-81 A.

Subsequently, i t was deter-l mined. that the subject valves had failed open.

These valve failures resulted in noncompliance l

with Technical Specification 2.6.(1)a.

Emergency i

Procedure EP-25, " Loss of Containment integrity",

I was immediately implemented.

The redundant out-board isolation valves, HCV-820A and 821A, were verified closed and operable.

LER-018 During the re-review of all electro pneumatic (E/P) valve positioners at the Fort Calhoun Sta-tion, the District determined that the Safety injection (SI) leakage cooler control valves l

PCV-2909, 2929, 2949, and 2969 should be included as part of the safety-related electrical equip-i i

ment that is environmentally qualified. This LER l

Monthly Op2rcticns R2 port October, 1982 Page Two A.

PERFORMANCE CHARACTERISTICS (Continued)

LER-018 (Continued) is being submitted based on the non-existence of analysis or test qualification data for these Honeywell Model No. 67400-023 positioners and the consequences of failure of these positioners.

Their failure could result in the opening of the subject valves due to instrument air leakage and, thus, provide a potential path for diverting part of the required Si flow from the reactor during an accident situation. The District is reporting this potential problem as required by lE Bulletin 79-018 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 01-1588 ST-ERM-1 Environmental TLD located within the DeSota township was found missing at collection time.

01-1589 ST-ESF-5 Timer for SI-2B out of specification.

01-1465 ST-CONT-3, While performing Containment isolation Valves, F.I leakage rate testing Type C penetrations M-2 and M-4 were found beyond maximum leakage allowed.

01-1377 ST-PORV-1 While performing ST-PORV-1, the PORV's opened when HC-102/lA was placed in " Test" position.01-957 ST-RM-2, During the performance of ST-RM-2, F.1, Annual F.1 Calibrations were found out of specification for RM-053, 0548, 55, 56A, 56B.

r Monthly Opsrstions Report October, 1982 Page Three C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (Continued)

Operations incident Deficiency 01-1594 ST-ESF-11, B/PIC-905 failed to " Reset" from tripped F.1 Condition at the appropriate setpoint.

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-TSCFP-1 Technical Support Center Fire Protection System Hydrostatic Test. Test showed no leakage.

This procedure did not constitute an unreviewed safety question because it only provided for a hydrotest of a portion of the fire protection system.

The requirements of Technical Specifica-tion 2.19 were followed.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

10-11-82 This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved evaluating data from a surveil-lance test.

E.

RESULTS OF LEAK RATE TESTS NONE F.

CHANGES IN PLANT OPERATING STAFF Phillip Avery was added to our Operations Department in the month of October.

G.

TRAINING NRC licensed personnel and license candidates attended Combustion Engineering simulator.

Nen licensed operators had fire brigade and systems training.

Maintenance personnel received systems training, additional emergency response training and a safety meeting was conducted.

}

Monthly Oparations R2 port October,1982 Page Four H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 NONE ll. MAINTENANCE (Significant Safety Related)

M. O. #

Date Description Corrective Action 16385 8-30-82 Fire Pump FP-1B clean heat exchanger Canpleted.

on coolant system.

16381 9-21-82 Replace heat exchanger regulator on Completed.

Fire Pump FP 18.

16368 8-25-82 HCV-884A will not give closed initla-Adjusted limit switch.

tion.

14058 3-2-82 Fire Pump FP-1B will not hold packing.

Installed upper packing.

~

16678 10-1-82 DTR-lll/121 AT for loop reading 30F Replaced recorder amp.

low.

16581 9-20-82 Charging Pump CH-1A packing leaking Completed HP-CH-1.

excessively.

16188 10-18-82 Raw Water Pump AC-10-C overhaul.

Completed per procedure AC-10-1.

16927 10-24-82 ICI Flange tighten all nuts.

Completed per procedure.

&. 5 &

W. G. Gates Plant Manager