ML20032E959

Monthly Operating Rept for Oct 1981

ML20032E959
Person / Time
Site:	Fort Calhoun
Issue date:	11/13/1981
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
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ML20032E956	List: ML20032E955 ML20032E959
References
NUDOCS 8111230541
Download: ML20032E959 (9)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

- 5 UNIT Fort Calhoun #1 November 13, 1981 DATE R. W. Short COMPLETED BY TELEPriONE (402)S36-4543 October, 1981 l

MONE DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 0.0 0.0 1

,7 0.0 0.0 2

18 3

0.0 0.0 i9 4

0.0 0.0 20 5

0.0 0.0 21 6

0.0 0.0 22 7

0.0 0.0.

23 8

0.0 0.0 2,

9 0.0 0.0 25 10 0.0 0.0 26 0.0 0.0 11 3

0.0 0.0 12 28 13 0.0 0.0 29 14 0.0 0.0 39 0.0 0.0 15 3,

0.0 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day in the reporting :nonth. Compute to the nearest whole rnegawatt.

(9/77 )

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OPERATING DATA REPORT DOCKET NO. _50,-285 DATE November 13, 1981 CO.\\lPLETED BY R. W. Short TELEPl!ONE (402)b36-4543 OPERATING STATUS Fort Calhoun Station-Unit No.1 Notes

1. Unit Name:

October, 1981

2. Reporting Period:

3. Licensed Thermal Power (AlWt):

1500 501

4. Nameplate Rating (Gror MWe):

5. Design Electrical Rating (Net 31We):

501

6. 31asimum Dependable Capacity (Gross 31We):

470

7. 31aximum Dependable Capacity (Net 31We):

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

N/A N/A

9. Power Level To Which Restricted. lf Any et.\\lWe):

10. Reasons For Restrictions. If Any:

This Sionth Yr to.Date Cumulative j

11. Hours in Reporting Period 745.0 7,296.0 71,017.0

12. Number Of Hours Reactor Was Critical 0.0 6,130.6 55,908.9 i

13. Reactor Re.,erse Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 0.0 6,080.3 54,840.2

15. Unit Reserve Shutdown Hours 0.0 0.0 U.U

16. Gross Thermal Energy Generated (\\lWH) 0.0 6.728.000.2 66,446,240.5

17. Gross Electrical Energy Generated (N1WH) 0.0 2.200,498.0 21,988m769.6

18. Net Electrical Energy Generated (alWH) 0.0 2,069,985.6 20,768,168.5

19. Unit Service Factor 0.0 83.3

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20. Unit Avaihbility Factor 0.0 83.3 77.2

21. Unit Capseny Factor (Using SIDC Net) 0.0 59.1 63.9

22. Unit Capacity Factor (Using DER Net) 0.0 59.1 63.5

23. Unit Forced Outage Rate 0.0 2.9 3.9

24. Shutdowns Scheduled Over Next 6 alonths(Type.Date.and Duration of Each1:

None 1

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

November 29, 1981

26. Units in Test Status (Prior o Commercial Operation):

N/A Forecast Achiesed INITIA L CRITICALITY l

INITIA L ELECTRICITY CO\\i\\1ERCIAL OPERATION (9/77)

50-285 DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCllONS UNIT NAME Fort Calhoun #1 DATE November 13. 1981 COMPLETED ilY R. W.

5hort REPORT MONTli October, 1981 1EMPilONE _ (402)536-4543 T

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1 N/A N/A N/A Reactor shutdown for annual refueling and maintenance outage.

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4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data ll Maintenance or Test 2-Manuai Scram.

Entry Sheets for I.icensee C-Refueling 3 Automatic Scram.

Event Report (LE80 File (NUREG-D Regulatory Restriction 4-Ot her ( Explain) 0161)

E-Operator Training & License Examination F Adnunistrative 5

G-Operational Error (Explain)

Esinbit I Same Source (9/77) 11 Other (Explain)

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Refueling Information j

Ebrt. Calhoun - Unit No.1 Report for the month ending October 1981 4

1.

Scheduled date for next refueling shutdown.

Deccaber 1, 1982

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2.

Scheduled date for restart following refueling.

March 1, 1983 3.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendmnt?

Yes i

a.

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

4 A Techninl Specification change.

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b.

If arser is no, has the reload fuel design ani core configuration been reviewed by i

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 infonnation.

September 1, 1982 5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis mthods, significant changes in fuel design, new l.

operating procedures.

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6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 l

d) planned spent fuel pool storage capacity 483 7.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

1985 i

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 October 1981 Monthly Operations Report I.

OPERATIONS

SUMMARY

The refueling outage continued during the month.

Care loading for Cycle Seven was completed.

Operations supported all phases of refueling operations as well as other special =aintenance activities.

No safety valve or PORV challenges occurred.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 81-009 During cold shutdown, containment cooling fan / coil VA-TC/VA-8A vas placed in service to provide con-tainment air cooling. When pressurized, a Cc=ponent Cooling Water (Auxiliary Coolant) leak cevelc;ed in coil VA-8A when a coil end plug blev out.

The loss of the cooling coil end plug caused a spill of 100 to 200 gallons of Auxiliary Coolant inside the Con-tainment. Once the source of the leak was deter-

=ined, coil VA-8A was isolated to ter=inate the leak.

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 surveillanc.e test schedule. The following is a sumenry of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incidents Deficiency OI-1383 ST-ERM-1, Unable to get well sample as specified RM-1 in Surveillance Test.

OI-1387 ST-ESF-3, Containment Pressure Sensors A/Th2-1, F.2 A/742-2, B/Th2-1, B/Th2-2, C/Th2-2, D/Th2-1, D/Th2-2 out of tolerance.

Monthly Operations Report October 1981 Page Two C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (Continued)

Operations Incidents Deficiency OI-1388 ST-RPS-8, High Containment Pressure Channel A/PC-F.2 765, C/PC-765, D/PC-765 out of specifi-cation.

OI-lh07 ST-ESF-8 LT-290hY, LT-292.kY, CT-29hhY and LT-296hY out of tolerance.

D.

CHA'IGES, TESTS AND EXPERIEME'ITS CARRIED OUT WITHCUT CCMMISSION APPROVAL Procedure Description SP-GRIND-1 The work done under this procedure does not con-stitute an unreviewed safety question as defined by 10CFR50.59 as it only invclved the preparation of a piping surface for inspection required by Technical Specification 3.3 in accordance with the ASME Boiler and Pressure Vessel Code.

SP-ISI-The work done under this procedure does not con-SURFPREP-1 stitute an unreviewed safety question as defined by 10CFR50.59 as it only involved the preparation of a piping surface for inspection required by Technical Specification 3 3 in acecrdance with the ASME Boiler and Pressure Vessel Code.

SP-ISI-The work done under this procedure does not con-SURCHPREP-1 stitute an unreviewed safety question as defined by 10CFR50.59 as it only involved the preparation of a piping surface for inspection required by Technical Specification 3,3 in accordance with the ASME Boiler and Pressure Vessel Code.

SP-FAUD-1 Fuel Assembly Uplift Core Detection.

An unreviewed safety question as defined in 10CFR50 59 did not exist as this procedure only involves evaluating data from a surveillance test.

E.

RESULTS OF LEAK RATE TESTS Annual leak rate tests are in progress.

A consolidated report will be made at the end of testing.

Monthly Operations Report October 1981 Page Three F.

CHA'iGES IN PLANT OPERATING STAFF NONE G.

TRAINING Training for Octcber included general employee training radiation protection training to support plant refueling modifications.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY CC'CIISSION AUTHORIZATION PURSUANT TO 10CFR50 59 NONE

e Monthly Operations Report October 1981 Page Four II.

MAINTENANCE (Significant Safety Relsted)

M.0.

Date Descrittien Corrective Action 10h82 9-30-81 VCPT Meter RPS "A" Channel mal-Replaced meter.

functioning.

9h22 10-2-81 Remove upper guide structure Relocated upper guide struc-lift rig to upper level for ture to southwest side of inspection.

containment.

12273 10-17-81 Perform polar crane check.

Polar crane checked per pro-cedure MP-HE-1-A.

9313 10-19-81 Replace spent fuel pool canal Spent fuel pool canal gate gate.

3placed per. procedure FH-16-2.

F 82 10-17-81 Change out Rav Water strainer AC-12A was changed out per 4

AC-12A.

procedure MP-AC-12.

11691 9-23-81 Short in C Channel RRS Hi h Repaired connectcr.

b Voltage Cable to Wide Range Drainer.

12187 10-12-31 HCV-506A failed shut.

Replaced blown fuse.

10133 9-26-81 Replace RC-23 sec. hand hole Replaced gaskets and covers.

covers.

10811 10-20-81 Replace pressuriser manway Completed per procedure.

per MP-RC h-3 9366 9-26-81 Replace secondary hand hole Installed new gaskets and covers per MP-RC-2-5-13 covers.

12291 10-25-81 HCV-250hB stuck in open Valve OK-faulty limit switch, position.

vere blocking contact.

Repaired - OK.

120h0 10-13-81 FI-330 has tubing leak.

Tightened fitting.

122h5 10-17-81 Leak in cooling coil VA-8A.

Retapped tubing and reinserted plug into tubing. Hydroed system.

12322 10-23-81 Clean Reactor Vessel Head Cleaned Reactor Vessel Flange Flange and install 0-Rings.

and installed 0-Rings per MP-RC-6 12215 10-13-81 Manual Operator on HCV-2883A Operator disengaged.

l vould not disengage from manual operation.

I

. s Monthly Operations Report October 1981 Page Five-II.

MAINTENANCE (Significant Safety Related)

M.O. #

Date Descrintion Corrective Action 9h09 10-2h-81 Replace hold down ring.

Hold down ring replaced per procedure MP-RC-7-3-B.

11941 10-2h-81 Remove Steam Generator "A" Manvay covers opened per Secondary manvay covers.

procedure MP-RC-2-2-A.

11575 10-21-81 Remove Alignment Pins.

Alignment pins removed per procedure MP-RC-6-5-A.

119h3 10-2h-81 Re=ove "B" Steam Generator Secondary manvay covers secondary manvay covers.

removed per procedure MP-RC 2-A.

93k9 10-2h-81 Clean Reactor vessel Flange.

Cleaned Reactor Vessel Flange per procedure MP-RC-1-3 9390 10-5-81 Install alignment pins.

Alignment pins installed per procedure MP-RC-6-5-B.

9312 10-7-81 Remove spent fuel pool canal Removed gate and stored on gate.

rack in transfer canal per procedure FH-16-1.

12086 10-8-81 Remove Reactor Vessel Head Head Lift Rig removed and Lift Rig.

stored.

9hh7 10-lh-81 Remove missile shields.

Missile shields removed and placed in storage area.

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Approved By:

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4 Inager - k rt Calhoun Station l

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