ML20235W996

Monthly Operating Rept for Sept 1987

ML20235W996
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-678, NUDOCS 8710190158
Download: ML20235W996 (10)

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'6, AVE' RAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285

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' UNIT- Fort Calhoun. Station DA'E T October 7, 1987 COMPLETED BY T. P. Matthews .

TELEPHONE .- 402-536-4733 MONTH September, 1987' DAY- AVERAGE DAILY POWER LEVEL' DAY AVER AGE DAILY POWER LEVEL (MWe-Net) ,(MWe-Net )

3 4RL O 17. 484.5 2 483.3 18 485.5 3 483.1 i9 485.9 g 482.3 20 486.9 5

. 482.2 487.1' 21 g,

481.5 ,, 487.1 7

481.2 23 486.4 8,

480.7 ,,3 486.2 481.7 485.9 9 23 to 483.4 23 485.0

o. 483.4 484.5 3 27

~483.3 484,1 12 28 13 484.0 29 484.2 g 483.7 485.3  ;

30 I5 483.6 3, g 484.0 INSTRUCTIONS

.'On this fermat, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9 /77 )

8710190150 070930 DR ADOCK 05000205 PDR 1EM l

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OPERATING DATA REPORT f DOCKET NO. . 50-285 _

l DATE m o m /, 1987,  !

COMPLETED BY I. F. Matthews {

TELEP110NE 402-536-4733- l

. OPERATING STATUS Fort Calhoun Station Notes

1. Unit Name:

2. Reporting Period: September 1987 1500

. 3. IJcensed Thermal Power (MWt):

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

9. Power Level To Whl:h Restricted,if Any (Net MWe): "!b

10. Reasons For Restrictions,If Any:

This Month Yr..to-Date Cumulative

' 11. Ifours in Reporting Period 720.0 ,,.

6,551.0 122,857.0 4,399.3 94,630.8

12. Number Of flours Reactor Was Critical 720.0 _

13. Reactor Reserve Shutdown flours ___ % G 0.0 1,309.5

14. flours Generator On.Line 720.0 4,322.7 93,709.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWil) 1,073,962.0 6,195,123.8 121,245,625./ .

17. Gross Electrical Energy Generated (MWH) 365,062.0 <

_2,076,409.0 39,843,135.2

18. Net Electrical Energy Generated (MWil) 348,568.2 1,980,168.0 38.063,628.9

19. Unit Service Factor 100.0 66.0 76.3

20. Unit Availability Factor 100.0 66.0 76.3

21. Unit Capacity Factor (Using MDC Neu _

101.3 63.2 66.9

22. Unit Capacity Factor (Using DER Net) 101.3 63.2 65.1

23. Unit Forced Outage Rate 0.0 0.0 3.2

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Eacht:

None

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

26. Units in Test Status OYior to Commercial Operation): Forecast Achieved INITI A L CRITICA LITY INITIAL ELECTRICITY N/A COMMERCIAL OPER ATION f

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Refueling . Information Fort Calhoun - Unit No.-1.

f Report for..the month ending Auaust 1987 .

1. Scheduled date for next refueling. shutdown. Seotember 1988

2. Scheduled.date for restart following refueling. December 1988

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?

Possible transition to 24 month cycles. ,

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. Auaust 1988

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 j operating procedures.

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6. The number of fuel assemblies: a) in the core 133 assemblies I b) in'the spent fuel pool 393 "

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c) spent fuel pool storage capacity 729 "

d) planned spent fuel pool May be increased "

storage capacity via fuel ein "

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 CM Date September 28, 1987 l

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

1. OfERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power throughout September, '1987.

Construction continues on the training facility, warehouse, maintenance l shop and parking lot.  !

NRC inspections were performed on Detailed Control Room Design Review (DCRDR), Safety Parameter Display System (SPDS) and Radiological and j Environmental Controls.

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 Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection. j i

This procedure did not constitute an unreviewed I safety question ar defined by 10CFR50.59 since it only involved thc 2 valuation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist. Results were I reviewed for July, August and September, 1987. I I

I L Monthly Operations Report j E September, 1987 l

-Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Committee Packages for September, 1987:

Packaae Description / Analysis  !

EEAR FC-85-119 Cold Laboratory Safety Shower.

This modification provided for the installation of a shower in the cold lab. This modification does i not have an adverse effect on the safety analysis.

l EEAR FC-85-102 Shutdown Cooling Heat Exchanger RTD Upgrade. l This modification provided for replacement of the [

RTD's for the shutdown cooling heat exchanger '

outlet temperature with qualified RTD's to meet the requirements of Reg. Guide 1.97. This modification does not have an adverse effect on the safety analysis. )

EEAR FC-86-018 Halon System for Cable Spread Room.

i This modification provided for a method of i installing and testing the two manual pull i stations for the cable spread room. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-203 ATWS Rule Modification. '

This modification provided for indication of RCS pressure consistent with pressures anticipated for an anticipated transient without scram (Reg. Guide 1.97). This modification does not have an adverse effect on the safety analysis. j EEAR FC-85-099 Containment Ambient Air Temperature RTD Upgrade.

This modification provided for the installation of four new instrument loops to monitor the ambient air temperature in containment to meet the requirements of Reg. Guide 1.97. This modification does not have an adverse effect on the safety analysis.

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Monthly Operations Report

. September, 1987 Page Three  ;

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

System Acceptance Committee Packages for Septen.ber,1987:

(Continued)

Packaae Description / Analysis EEAR FC-86-041 ASCO Solenoid Valve Change Out on Nitrogen and Safety Injection System.

This modification provided for the replacement of nine solenoid valves. These replacements were upgrades to. comply with the EEQ rule due to maintenance. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-101 Shutdown Cooling Flow Transmitter Upgrade.

This modification provided for the one-for-one replacement of FT-326, shutdown cooling flow transmitter. This replacement was necessary to meet the qualification requirements of Reg. Guide 1.97. This modification does not have an adverse <

effect on the safety analysis. '

EEAR FC-85-098 Quench Tank Pressure Transmitter Upgrade.

1 This modification provided for the installation of an expanded range (0-100 psig) pressurizer quench tank pressure transmitter in order to meet the requirements of Reg. Guide 1.97. This modification does not have an adverse effect on the safety analysis.

E:AR FC-83-002B FH-1, FH-12, FH-13 Drive Controller Part 2 This modification provided for the installation of new electronic bridge, trolley and hoist drive units. These units provide better control for fuel handling machine operations. This modification does not have an adverse effect on the safety analysis.

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Monthly Operations Report j h September, 1987 "

Page Four.

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

' System Acceptance Committee Packages for September, 1987:

-(Continued)-

Packaae Description / Analysis EEAR FC-86-056 EFWST Nitrogen Supply.

This modification-provided for the relocation of a pressure. reducing station for the EFWST nitrogen supply to the top of the tank. 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 None G. TRAINING During September, Station. Training started senior reactor operator upgrade training for four employees, completed the technical staff training program, conducted licensed operator requalification training, and continued trrining for shift technical advisors and non-licensed operators.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 4 Amendment No. Description 111 This amendment incorporates revised Surveillance Requirements for the diesel generators in accord-ance with Generic Letter 84-15 entitled, " Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability."

This amendment is effective October 24, 1987, which is 30 days from date of issuance (September 24,1987).

Monthly Operations Report September, 1987 Page Five II. MAINTENANCE (Significant Safety Related)

None ,

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W. Gary Gates ,

Manager-Fort Calhoun Station '

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l Omaha Public Power District 1623 Hamey Omaha, Nebraska 68102 402/536-4000 October 13, 1987 LIC-87-678 i

5 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 y 35g j o a !

Reference:

Docket No. 50-285 >

Gentlemen: o 9

SUBJECT:

September Monthly Operating Report '

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

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

Since ly, R. L. Andrews Division Manager  ;

Nuclear Production l RLA/me Enclosures c: NRC Regional Office Of fice of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INPO Records Center American Nuclear Insurers l l NRC File (FCS) l i

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