ML20211D480

Monthly Operating Rept for Jan 1987

ML20211D480
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-87-098, LIC-87-98, NUDOCS 8702200450
Download: ML20211D480 (9)

Text

i AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Calhoun Statio3 DATE Fahruary 11. 1987 T. P. Matthews COMPLETED BY TELEPHONE 402-536-4733 MON 1y January, 1987 f'

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

(MWe-Net) 1 487.6 37 487.2 487.5 2

18 487.2 487.6 487.2 3

i, 4

487.8 20 487.1 5

487.5 21 487.4 487.4 487.0 6

22 7

23 486.7 8

487.4 486'.'/

24 487.2 9

25 486.8 487.3 10 26 441.7 11 487.3 27 236.5-437.2 348.7 12 28 487.1 472.1 13 29 14 487.3 486.7 30 486.9 488.6 15 3,

16 487.1 l

il INSTRUCTIONS On this format. fist the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO. En ?AR DATE February 11, 1987 COMPLETED BY T. P.-Matthews TELEPHONE an?-9 L 4733' OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Notes

2. Reporting Period:

January, 1987 1500

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

502

3. Design Electrical Rating (Net MWe):

478 502

6. Maximum Dependable Capacity (Gross MWe):

478

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 Level To Which Restricted. If Any (Net MWe):

N/A

10. Reasons For Restrictions.lf Any:

Nnne This Month Yr. to Date Cumulative i1. Ilours in Reporting Period 744.0 744.0 117.050.0

12. Number Of Hours Reactor Was Critical 744.0 744.0 90,975.5

13. Reactor Resene Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 744.0 744.0 90.131.1

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Gmss Thermal Energy Generated (MWH) 1,091,036.5 1,091,036.5 116,141,538.4

17. Gross Electrical Energy Generated (MWH) 367.850.0 367.850.0 38,134,576.2

18. Net Electrical Energy Generated (MWH) 351,732.0 351,732.0 36,435,192.9

19. Unit Senice Factor 100.0 100.0 77.0

20. Unit Availability Facto, 100.0 100.0 77.0

21. Unit Capacity Factor (Using MDC Net) 98.9 98.9 67.4

22. Unit Capacity Factor (Using DER Net) 98.9 98.9 65.4

23. Unit Forced Outage Rate 0.0 0.0 3.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each)

The 1987 Refueling Shutdown is tentatively scheduled for March 6,1987 with Startup tent'atively scheduled for May 7,1987.

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

26. Units in Test Status I, Prior io Commercial Operation):

Forecast Achiesed INITIA L CRITICAt_ITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

50-285 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Fort Calhoun Sta' tion DATE Fahruary 11. 1987 COMPLETED BY T. P. Matthews REPORT MONTH ilanuary. 1987 TELEPHONE 402-536-4733 "E

-k Cause & Corrective

.$ 3 3

h.Yk Licensee

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255 Event u7 i

Action to

$5 5

j@g Report =

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Prevent R-rrence 6

87-01 870126 S

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4 N/A SG Condxx On January 26, 1987, a educ-3 tion comenced to dete' icakage in "A" North Condensor

- ower was held at 55% while the corcensor was I

checked. Condensor leaks were iden-tified, and 7 tubes were plugged.

The unit returned to full power on January 30, 1987.

1 l

I 2

3 4

s F: Forced Reason:

Method:

Exhibit G-Instructions l

S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data l

B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (i.ER) File (NUREG.

l D-Regulatory Restriction 40ther (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G Operational Error (Explain)

Exhibit I - Same Source (9/77) 110ther (Explain) l l

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R:fu211ng Inf:rmation Fort Calhoun - Unit No. 1 Report for the month ending January 1987 1.

Scheduled date for next refueling shutdown.

February. 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?

Fuel supplier change from ENC to CE and possible Technical Specification change.

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.

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.

New fuel supplier (Combustion Engineering) but the new fuel will be es.:entially the same as that supplied by Combustion Engineering for Cycle 5.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in tha spent fuel pool 349 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel oin consolidation 7.

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

1996 Prepared by _U N e Date January 30. 1987 m

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 January, 1987 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power until January 27, 1987, when power was reduced to 55% for leak testing the condenser tubes.

The tube leak was plugged and 100% power was resumed January 29, 1987. All of the i.ew control element assemblies and the first of four loads of new fuel for Cycle 11 arrived on site.

Two waste concentrate liners were solidified.

Two Auxiliary Operators-Nuclear (A0N's) were hired and one A0N resigned during January, 1987.

Training continued for Equipment Operator Nuclear-Turbine Building and the four member SR0 upgrade class.

In addition, refresher training continued for nonlicensed operators and the first technical staff training program was successfully completed.

Simulator training at the Combustion Engineering PWR training facility in Windsor, Connecticut, began January 5 and continued through the month.

No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Qescription SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed i

safety question as defined by 10CFR50.59 since it i

only involved the evaluation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist.

Monthly Operations Report January, 1987 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description SP-VA-80 Hydrogen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only involved the verification of operability of the hydrogen purge system.

System Acceptance Committee Packages for January, 1987:

Packaae Description / Analysis EEAR FC-83-178 FH-12 Drive System.

This modification provided for the installation of new clutches and a larger 3/4 HP motor on the bridge drive of FH-12. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-193 Improved EHC Lighting.

This modification provided for the installation of a two tube fluorescent light fixture above the EHC unit.

This modification does not have and adverse effect on the safety analysis.

EEAR FC-84-195 Sewer Line Replacement.

This modification provided for the replacement of the auxiliary building sewer line. This modifica-tion does not have an adverse effect on the safety analysis.

EEAR FC-85-052 Relocate Alarm - Room 115 TSC.

This modification provided for the relocation of an emergency alarm from inside Room 115 to the TSC hallway.

This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-058 Alteration of Annunciator Window A-1U.

This modification provided for the change out of annunciator windows A-lu, A-5U, B-9, A-3U, A-3L, B-3U and B-3L.

This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report January, 1987 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMTSSION APPROVAL (Continued)

System Acceptance Committee Packages for January,1987:

(Continued)

Packaae Description / Analysis EEAR FC-85-176 Low Dilution Water Flow During Regeneration.

This modification provided for the replacement of internal gears of pumps with gears which doubled pump stroke speed, which has the effect of doubling pump capacity. The pumps modified were i

DW-37A and DW-378. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-208 Replacement of HCV-2805A & B.

This modification provided for the replacement of raw water strainer backwash valves with pinch type valves. This modification does not have an adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS None.

F.

CHANGES IN PLANT OPERATING STAFF During January, one Auxiliary Operator-Nuclear resigned (Dennis Peters) and two Auxiliary Operators-Nuclear were hired (Larry Hautzinger and Russ Huber).

G.

TRAINING Training continued for Equipment Operator Nuclear-Turbine Building and the four member SRO upgrade class.

In addition, refresher training continued for nonlicensed operators and the first technical staff training program was successfully completed.

Simulator train-ing at the Combustion Engineering PWR training facility in Windsor, Connecticut, began January 5 and continued through the month.

r.

Monthly Operations Report January, 1987 Page Four H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.

Descriotion 102 The amendrrent deletes the short term reporting requirements related to primary coolant specific activity levels and no longer requires plant shutdown if the primary coolant specific activity exceeds the limit of I.0 microcurie / gram dose equivalent I-131 for an accumulated period over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period.

II. MAINTENANCE (Significant Safety Related)

None T. (

v W. Gary Gates Manager-Fort Calhoun Station

Omaha Public Power District 1623 Harney Omaha. Net >raska 68102 2247 402/536 4000 February 13, 1987 LIC-87-098 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

January 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 January,1987 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, d

W R. L. Andrews Division Manager 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)

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