ML20083N352

Monthly Operating Rept for Mar 1984

ML20083N352
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1984
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-84-111, NUDOCS 8404190163
Download: ML20083N352 (10)

Text

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Statio:

DATE April 13, 1984 COMPLETED BY T. P. Matthews TELEPHONE (402) 536-4733 MONTH March, 1984

. DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) _ (MWe-Net) i 341.8 0.0 37 2 232.4 18 0.0 3 0.0 39 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0. 0 ,

8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0

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13 0.0 . 29 - 0.0 g4 0.0 0.0 30 15 0.0 31 0.0 16 0.0 4

INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute io the nearest whole megawatt.

(9/77I 8404190163 840331 PDR ADOCK 05000285

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• OPERATING DATA REPORT DOCKET NO. 50-285 DATE Anril 13,1984 COMPLETED BY T. P. Matthews TELEPil0NE (402) 536-4733 OPERATING STATUS Fort Calhoun Sution Notes

1. Unit Name:

2. Reporting Period: I ' 1904 1500

3. Licensed Thermal Power (MW ):

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 470

6. Maximum Dependable Capacity (Gross MWe): 4

7. Maximum Dependable Capacity (Net MWe):

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

N/A .

9. Power Lesel To Which Restricted. If Any (Net MWe): N/A

10. Reasons For Restrictions,if Any: None This Month Yr..to.Date

• Cumulative .

II.' Hours in Reporting Period . 744.0 2,184.0 92,186.0

12. Number OfIlours Reactor Was Critical 50.2 1,490.2 71,384.1-

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.0

14. Hours Generator On.Line 49.5 1,489.5 70,892.0

15. Unit Reserve Shutdown Hours 0.0 0.0- 0.0

16. Gross Thermal Energy Generated (MWH) 49,026.4 2,152,796.9' 88,912,510.6 .

17. Gross Electrical Energy Generated (MWH) 14,816.0. 690,258.0 29,007,827.0

18. Net Electrical Energy Generated (MWH) 13,781.8 656,536.5- 27,736,405.2

19. Unit Service Factor 6.7 68.2 -76.9

20. Unit Availability Factor 6.7 68.2 76.9 4.2 68.5

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21. Unit Capacity Factor (Using MDC Net) 65.6

' 22. Unit Capacity Factor (Using DER Net) 3.9 62.9 63.3

23. Unit Forced Outage Rate 0.0 0.0- 3.5 '

24. Shutdowns Scheduled Over Ne.st 6 Months (Type. Date.and Duration of Each1:

s

25. If Shut Down At End Of Report Period.Estimaied Date of Startup: May 1, 1984

26. Units in Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY ~

COMMERCIAL OPERATION (9/77 )

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DOCKET NO.

50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS ,

Ebrt Calhoun Station UNIT NAME DATE April 13,1984 COMPLETED BY T. P. Matthets REPORT MONDI March. 1984 TELEPHONE (402) 536-4733 0 i.

, .[ g 'h .E Licensee $g c. Cause & Corrective No. Date g 3g j jgE Event g? g3 Action to F

$= $ jgg Report a mV g

U Prevent Recurrence d

84-01 840303 S 694 C 4 N/A XX XXXXX 1984 refueling outage cmmenced March 3, 1984.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Inst ructions S: Scheduled A Equipment Failure (Explain) . I-Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Repor (Li'R) File (SUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Eshibii 1 - Same Source (9/77) ll-01her (Explain)

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Refueling Information Ebrt Calhoun - Unit No.1 l

Beport for the nonth ending March 1984 . l I

1. Scheduled date for next refueling shutd m n. September 1985 l

2. Scheduled date for restart following refueling. November 1985

3. Will refueling or resumption of operation thereafter require a technical specification change or o,ther '

license amendment? Yes

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

Technical Specification change

b. If answer is no, has the reload fuel design

^ and oore (onfiguration been reviewed by your Plant Safety Review Cbmnittee 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 data (s) for submitting proposed licensing action and support information. Annnet 1m

5. Inportant li nsing considerations associated with refueling, e.g., new or different fuel design or ,

supplier, unreviewed design or performan analysis .

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

6. The number of fuel assenblies: a) in the' core _

133 ~ assemblies-b) in the spent fuel pool 305 c) spent fuel pool a

storage capacity 729 d) planned spent fuel pool-storage capacity *

• may be increased via fuel pin consolation

7. . 'Ihe projected date of the last refueling that can be discharged to the_ spent fuel pool assuming the present-

. licensed capacity. -

1996-Preparedbyh rMA 'Date Aoril 1. 1984 e i .

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OMARA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 March, 1984 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station went of f line March 3,1984, for a scheduled maintenance and refueling _ outage.

Several major jobs which were completed or are in progress during March include:

1. All four reactor coolant pumps had seals and case-to-cover gaskets

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replaced.

2. Eddy current testing was performed on both steam generators.

3. Both steam generators have been sludge lanced.

4. The reactor vessel head has been removed and preparations are under way to begin fuel movement.

5. The five year inspection has been performed on the main generator.

6. Inspection and repair on the turbine continues along wjth installation of the new high pressure turbine rotor.

No safety valve or PORY challenges occurred.

A. PERFORMANCE CHARACTERISTICS

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None B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None e ,

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. Monthly Oparations Report March, 1984 Page.Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description

-SP-NFR-1 Fuel Receipt Procedure.

This procedure did not . constitute an unreviewed safety question as defined by 10CFR50.59 because new fuel was received and inspected in accordance with approved procedures and the limitations of the Station operating license.

SP-PORV-2 ,

PORY Setpoints.

This procedure did not constitute an unreviewed safety ouestion as defined by 10CFR50.59 because it was completed as planned using normal plant procedures.

i SP-FIL-2 Inspection and Pressure Drop Measurement for Technical Support Center Cooling and Filtering Unit.

This procedure did not constitute an unreviewed safety i' question as defined by 10CFR50.59 because it did not i involve safety related equipment.

System Acceptance Committee Packages for March,1984:

Package Description / Analysis EEAR FC-83-100 Chemistry Hot Lab Vacuum Pump Installation.

This modification is not safety related; therefore, has- ,

no adverse effect on the ' safety. anal'ysis.-

EEAR FC-78-20 Generator Trip with Generator Breaker Mod. Open.

This inodification makes it so that the generator breakers will not close out of synchronization and cause a large- transient.- This modification has no-adverse effect on the safety. analysis.

EEAR FC-79-134- Piping from Room 59 to Switchgear-Room for' Containment Leak Rate Test. .

This modificatio prevents having to run ins'trument.

piping through fire doors when perfoming the 60 psi ~

containment leak rate -test. This: modification has no..

- adverse effect on the safetyLanalysis.

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fionthly Operations Report March, 1984 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Canmittee Packages for March,1984: (continued)

Procedure Description EEAR FC-79-92 Secondary Plant Sampling System.

This modification is not safety related; therefore, has no adverse effect on the safety analysis.

EEAR FC-79-87 _ Installation of Additional Gai-tronics Stations.

This modification is not safety related; therefore, has no adverse effect on the safety analysis.

EEAR FC-80-02 Load Lifting Eye.

This modification is not safety related; therefore, has no adverse effect on the safety analysis.

EEAR FC-79-38 Containment Ventilation Modification for Low Volume Flows.

This modification improves the control over the -

containment purges for-low volume flows. This modification has no adverse effect on the safety analysis.

EEAR FC-80-133 Modification of-Health Physics' Work Area.

This modification-involved relocation of a' detector.

This detector. is to be verified operable by CP-FDZ-6 after it is reinstalled. This change will not effect its operability and the requirements of Technical ~

Specification-2.19.1 will be met.. This modification.

has no adverse _ef fect on-the. safety analysis. t

'EEAR FC-82-82 Lift Rig for Containment Recirculation Strainer Baskets.

This ' modification provided for the fabrication of ' lift rig for containm6nt recirculation ' strainer' baskets.

This ' device is used to lift the strainer baskets =when the plant is in a shutdown condition. This

- modification has no adverse effect on the safety analysis.

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Monthly 0parations Report March, 1984

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Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for March,1984: (continued)

Procedure Description EEAR FC-80-6 Mast Rotate / Spreader Interlock.

This modification provided for the installation of extra s-*cty interlock on PAR refueling machine. This modification has no adverse effect on the safety

_anal ysi s.

EEAR FC-82-17 . Replacement of DG1 and DG2 Pressure Switches.

This modification will enhance the safety of the system by providing better quality equipment. This modification has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS'-

The Fort Calhoun Station is currently perfoming B anda C penetration

~ tests. A report will be sent out at the end of-the refueling outage.

F. CHANGES IN PLANT OPERATING STAFF Mr. Mark Gardner started March 27, 1984,- as an Auxiliary Operator -

Nuclear. -

G. TRAINING

. Training in March was directed thward outage requirements in the areas of..

General Employee Training, crane training, system hydro test training 'and'

. Job . briefings - fo r ' ALARA requi rements. .

One new ~ operator completed- five weeks"of initial. plant training.

_ H. . CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION

-AUTHORIZATION PURSUANT TO 10CFR50.59f

, None 4

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. . l Monthly Operations R: port

. March, 1984 Page Five II. MAINTENANCE (Significant Safety Related)

None MT. I W. Gary Gates Manager Fort Calhoun Station O

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. I Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 April 13, 1984 LIC-84-111 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docke t No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the March Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely,

.t lk!Dw W. C.iJones w

Division Manager Production Operations WCJ/TPM:jmm Enclosures cc: NRC Regional Office l Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center NRC File

'fl 45.5124 Employmen h ouai 0pportunity