ML20206P739

Monthly Operating Rept for Mar 1987

ML20206P739
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-253, NUDOCS 8704210255
Download: ML20206P739 (8)

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,e g AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fnet ralhnnn Station DATE April 13, 1987 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 MONT11 March.' 10R7 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe Net t l I 490.2 37 0,0 2 490.0 18 0.0 3 490.2 , i, 0.0 489.9 4 20 0.0 5 488.8 21 0.0 6 465.3 22 0.0 7 35.0 nn 23 s 0.0 24 0.0 9 0.0 23 0.0 to 0.0 26 0.0 li 0.0 27 0.0 12 0.0 2g 0.0 13 0.0 29 0.0 i4 0.0 30 0.0 is 0.0 0.0 3

16 0.0 I

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 nwgawatt.

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(9/77i kgfE10235870333 R ADOCK 05000285 PDR 7

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OPERATING DATA REPORT DOCKETNO. 50-285 DATE April 13, 1987 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 OPERATING STATUS Fort Calhnun Statinn N88'8

1. Unit Name:

2. Reporting Period: March. 1987

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 478 ,

6. Maximum Dependable Capacity (Gross MWe): 502

7. Maximum Dependable Capacity (Net MWe): 478

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

N/A l

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

10. Reasons For Restrictions. lf Any: Nono i This Month Yr to Date Cumulative

• * * ~

11. Ilours In Reporting Period '

12. Number Of Hours Reactor Was Critical 154.8 1.570.8 91.802.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On.Line 151.0 1.567.0 90.954.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 218,683.0 2,301,386.5 117.351,888.1 .

17. Gross Electrical Energy Generated (MWil) 74,288.0 785,356.0 38,552,082.2

18. Net Electrical Energy Generated (MWil) 70,782.3 751,184.8 36.834,645.7 i 19. Unit Service Factor 20.3 72.5 76.8

20. Unit Availability Factor 20.3 72.5 76.8

21. Unit Capacity Factor (Using MDC Net) 19.9 72.8 67.2

22. Unit Capacity Factor (Using DER Net) 19.9 72.8 65.3

23. Unit Forced Outage Rate 0.0 0.0 3.3

24. Shutdowns Scheduled Over Next 6 MonthsIType. Date,and Duration of Each):

The 1987 Refuelina Shutdown commenced on March 7. 1987 with startup tentatively scheduled for May 26, 1987.

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

i 26. Units in Test Status tPrior to Commercial Operation): Forecast Achieved i

! INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMM ERCIA L OPER AT10N (9/77)

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UNITSHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-285 Fort Calhoun Station UNIT NAME DATE Anril 11. 1497 COMPLETED 3y T. P. Matthews REPORT MONTH March 10A7 TELEPHONE 4074 3Fi-4711

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, .5 E 3 jY3 Licensee ,Eg  % Cause & Corrective

-h Date g 3g is5 Event gy g3 Action to H

f s,5 jgg Report 2 mV g

O Prevent Recurrence 6

87-02 870307 S 593.0 C 1 N/A xx xxxxx The 1987 Fort Calhoun Station Refuel-ing Outage commenced March 7, 1987.

1 1 I 2 3 4 .s 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 (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

EOperator Training & Ucense Examination F-Administrative 5 G4perational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

Refu211ng Information Fort Calhoun - Unit No. 1 Report for the month ending March 1987 .

1. Scheduled date for next refueling shutdown. March 1987

2. Scheduled date for restart following refueling. May 1987

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?

(1) Fuel supplier change from ANF to CE.

(2) Increase core inlet temperature back to 545'F from 540*F (Cycle 10)

(3) Replacement of part length CEA's with nontrippable (full length) CEA's.

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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. submitted January 1987

5. Important 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 assemblies: a) in the core 0* assemblies b) in the spent fuel pool 526* "

c) spent fuel pool I storage capacity 729 "

, d) planned spent fuel pool May be increased "

storage capacity via fuel oin "

consolidation

• Currently in refueling mode - as of March 31, 1987 core had been off-loaded

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuning the present licensed capacity. 1996 Prepared by M Ab Date March 31. 1987

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. I March, 1987 Monthly Operations Report -

I.- OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power until March 7, 1987, when the plant was shut down for its tenth refueling and maintenance outage after a 195 day run.

During March,1987, the core has been off loaded and the fuel is currently undergoing a UT integrity inspection. The core support plate was vacuumed to pick up loose debris. Control element drive mechanism repair, reactor "

coolant system root valve replacement and repair, and loop injection valve repair are in progress.

Steam generator tube eddy current testing has indicated that no tubes need to be plugged. This improvement is apparently due to boric acid injection on the secondary side started this last cycle.

Both turbine low pressure rotors and upper and lower diaphragms have been removed for non-destructive testing and inspection. The turbine stop and (

intercept valves have also been disassembled. Eddy current testing was -

performed on condenser tubes and several of the feedwater heaters.

The turbocharger was replaced on one of the emergency diesel generators  ;

and replacement is in progress on the second diesel generator. Preventive maintenance and trip checks are almost complete on all 4160 volt breakers.

There was one shipment of radioactive waste offsite including two waste  ;

concentrate liners. ,

Two Auxiliary Operators-Nuclear were hired during March, 1987.

• During the month, an Equipment Operator-Nuclear Turbine Building training class was completed, and an Auxiliary Operator-Nuclear training class was started. SR0 upgrade exams were administered to four operators by the NRC. All four individuals passed. Oral requalification -exams were administered by the NRC to two SR0's; both passed. Licensed operator '

requalification and non-licensed operator refresher training continued.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS None I i

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Monthly Operations Report March, 1987 Page Two C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-BURNUP-1 Burnup Determination for Storage of Spent Fuel.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provides for calculating the burnup and acceptance for storage of spent fuel bundles in accordance with Technical Specifications. No equipment operability is affected.

SP-NFR-1 Fuel Receipt Procedures.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure provided for receipt, inspection and storage of new unirradiated fuel. Appropriate radiological and load handling limits were observed.

E. RESULTS OF LEAK RATE TESTS None.

F. CHANGES IN PLANT OPERATING STAFF Two Auxiliary Operators-Nuclear started in March, Steve Morrissey and Robin Fisher.

G. TRAINING During the month, an Equipment Operator-Nuclear Turbine Building training class was completed, and an Auxiliary Operator-Nuclear training class was started. SR0 upgrade exams were administered to l four operators by the NRC. All four individuals passed. Oral requalification exams were administered by the NRC to two SR0's; both passed. Licensed operator requalification and non-licensed operator refresher training continued.

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Monthly Operations Report March, 1987 Page Three H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Amendment No. Description 103 The amendment modifies the refueling boron concentration from at least 1700 parts per million (ppm) to at least 1800 ppm.

104 The amendment changes the surveillance criteria for Sample Selection and Inspection Results regarding steam generator tube inspections from fixed numerical criteria to comparable percentages.

106 The amendment modifies the surveillance requirements for the hydrogen and oxygen monitoring system for the waste gas decay tanks to clarify that a daily channel check is required for this system when it is in service.

107 The amendment deletes the hydrogen fluoride detectors from Tables 2-11 and 3-3 of the Technical Specifications. By NRC letter dated March 12, 1987, you were notified of the termination of Part 40 Materials License No.

SMC-1420 that authorized the possession of natural uranium hexafluoride at the Fort Calhoun site.

II. MAINTENANCE (Significant Safety Related)

A report of all significant safety related maintenance performed during the 1987 refueling and maintenance outage will be submitted at the end of the outage.

AV.

W. Gary Gates Manager-Fort Calhoun Station

Omaha Pubilc Power District 1623 Harney Omaha, Nebraska 68102-2247 402/536 4000 April 15, 1987 LIC-87-253 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

March Monthly Operating Report Gentlemen:

Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the March,1987 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, R. L. Andrews Divisior Manager h

Nuclear Production RLA/me Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File (FCS) 56VI r 8

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