ML20237J922

Monthly Operating Rept for Jul 1987

ML20237J922
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-569, NUDOCS 8708180407
Download: ML20237J922 (10)

Text

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AVER AGE DAILY UNIT POWER LEVEL 0 ,

DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE August 6,'1987-COMPLETED BY T. P. Matthews-TELEPHONE 402-536-4733-1

' MONTH: ' duly 1QR7

. DAY- AVERAGEI I POWER LEVEL DAY ^ AVERAGE DAILY POWER LEVEL (MWe-Net) 1 476.9' 17 '475.2 2 476.8 18 475.1 3 475.8- 474.8

.4- ' 470 n 20 474.3  :

5 476.1 21 472.0 6 477.7 22 472.3 7

476.2 472.5 23 8 474.9 - 24 471.7 9

474.4 471.6 25 10 474.8 471.5 26

474.3 27 470.0 12 475.4 467.6 28

13 476.9 29 46716 479.8 466.9 14 3o 38 31 466.7 16 476.8 INSTRUCTIONS i On this format list the average daily unit i,ower leselin MWe Net for each day in the reporting ruonth. Compute to the nearest whole megawatt, (9/77)

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9 OPERATING DATA REPORT-DOCKET NO. 50-285 DATE anmmt 6 1987 COMPLETED IlY . T.'P.Maf, thews TELEPil0NE 402-636-4733 OPERATING STATUS -

I.' Unit Name: Fort Calhoun Station- Notes

2. Reporting Period:

July, 1987

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502-

5. Design Electrical Rating (Net MWe): 00

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 Which Restricted,if Any (Net MWe): N/A

10. Reas<ms Fhr Restrictions,if Any: None This Month Yr..to Date Cumulative 744.0 5,087.0 121,393.0

11. Hours in Reporting Period

- 12. Number Of Hours Reactor Was Critical 744.0 2,935.3 93,166.8

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Hours Generator On.Line 744.0- -2.858.7 92,245.8

' 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 j

16. Gross Thermal Energy Generated (MWH) 1,109,338.7 4,011.066.9 119,061,568.8 . 1 369,772.0 1,339,301.0 39,10b,02/.2

.17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH) 352,609.0 1,276,601.2 37,360,062.1,

19. Unit Service Factor 100.0 56.2 /b.0

20. Unit Availability Factor 100.0 56.2 7. 0_

21. Unit Capacity Factor (Using MDC Net) 99.1 52.5 66

'22. Unit Capacity Factor (Using DER Net) 99.1 52.5 64.T 23.- Unit Forced Outage Rate 0.0 0.0 3.2

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

None J

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

26. Units in Test Status (Prior to Commercial Operation H Forecast Achieved INITIAL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION N/A (0/77) j

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Refueling Information Fort Calhoun - Unit No-.1 Report for the month ending. June 1987 .

.l. Scheduled date for next . refueling shutdot n. 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 operating procedures.

l

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

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 7d M Date July 28.1987 I

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r 0MAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 July, 1987 Monthly Operations Report i

I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power throughout July,1987. Region IV NRC inspections were performed on the annual emergency exercise, the ISI program, and radiological confirmatory measurements. A Washington NRC audit was performed on the e xiliary feedwater system.

Construction was started on the training facility and the new warehouse.

A Shift Supervisor was transferred to the Simulator Services Department, a '.

Reactor Operator was transferred to the Station Training Department, and a Reactor Operator was promoted to Shift Supervisor during July,1987.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGE 3 IN OPERATING METHODS None i

C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CAP.RIED OUT WITHOUT COMMISSION APPROVAL USAR - Section 8 - Cable Sizina '

i The USAR was updated to clarify Section 8.5.4(f) on cable sizing criteria. This section previously stated that cables nave been sized to meet 125% of full load criteria. The update states that in ,

general 125% of full load criteria, as indicated in the National Electric Code Article 430-22, was used. Based on a 10 CFR 50.59 evaluation, cables found to be sized to 121% of full load criteria do not constitute an unreviewed safety question. This USAR subsection is not cited as a basis for any Technical Specification.

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Monthly Operations Report July, 1987 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a surveillance test to verify that a fuel assembly uplift condition did not exist.

System Acceptance Committee Packages for July,1987:

Packaae Description / Analysis EEAR FC-79-131 Containment Roof Sealing.

This modification provided for sealing the l containment roof with a commercial roof sealant.  !

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

EEAR FC-83-175 Fecdwater Regulating System Instrumentation ,

Replacement.  !

l This modification provided for the replacement of I the feedwater regulating controllers, power supplies and transfer switches. These were unit-for-unit replacements. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-007 Making Temporary Lead Shielding. Permanent.

This modification provided for making temporary lead shielding a permanent installation. In all areas where the temporary lead shielding was made permanent, load and/or seismic analyses were performed to verify the weight of the lead shielding will not be detrimental to the associ-ated piping or any surrounding equipment. This modification does not have an adverse effect on the safety analysis, l

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Monthly Operations Report July, 1987 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for July, 1987: (continued)

Packaoe Description / Analysis EEAR FC-85-020 480V AC Outlet for Forced Air Fan Adjacent to Heater Drain Pumps.

This modification provided for the installation of a 480V AC outlet in the basement. An outlet was needed for the forced air fan adjacent to the heater drain pumps in order to keep the fan cord from laying across the floor. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-116 Replacement of Fire Door 1007-8.

This modification provided for the replacement and alarming of fire door 1007-8 in the auxiliary building. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-Olf, Incompatibility of Inverters and Bypass Transformers.

This modification provided for the installation of new bypass transformers for the safety related instrument inverters. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-052 Ventilation Housing Security Barrier.

This modification upgraded the security system.

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

EEAR FC-86-054 Barriers for Vent Openings on Room 81 Roof.

This modification upgraded the security system.

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

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Monthly Operations Report July, 1987 Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for July, 1987: (continued) ]

j Packaae Description / Analysis '

EEAR FC-86-092 Alterrex Adjustment /PSS Realignment.

This modification provided for the installation of a new AC regulator circuit board followed by alterrex adjustments and testing. The PSS will l also be realigned following alterrex modifica-tions. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-012 Replacement of Pressurizer Watts Transducers.

This modification provided for the replacement of 12 pressurizer watts transducers in panel AI-12 to provide devices with calibration capability.

Project was initiated by failure of one original device which failed to perform within performance requirements. This modification does not have an ,

adverse effect on the safety analysis. I EEAR FC-87-028 Failure of C/TE-112C.

This modification provided for wiring '.E-113 in place of'C/TE-112C that failed. This allowed C channel of the RPS to remain functional and the l' plant to remain at full power. This modification 4 does not have an adverse effect on the safety i analysis.

E. RESULTS OF LEAK RATE TESTS As part of the 1987 refueling outage, local leak rate tests were performed on the reactor containment building penetrations in accordance with the Fort Calhoun Station Technical Specifications (Section 3.5) and 10 CFR Part 50, Appendix J. The testing is performed to identify, measure and, if required, initiate maintenance on potential reactor containment leakage paths; and to ensure the total measured leakage does not exceed the Technical Specification limit of 0.6La, (La = leakage allowable and .6La = 62,951 standard cubic centimeters per minute). The initial "as found" local leakage rate was 68,526.3 sccm. The "as found" leakage for penetrations M-93, M-94 and M-95 did not contribute to actual leakage as the inside containment barrier was found intact. Therefore, the total "as found" leakage which contributed toward the .6La limit was 23,800.4 secm. The final "after maintenance" leak rate was 1074.2 sccm.

.i Monthly Operations Report

- July, 1987 Page Five F. CHANGES IN PLANT OPERATING STAFF During July,1987, Mr. Charles A. Carlson was promoted to Shift I Supervisor, Mr. James B. Michael was transferred to the Simulator l Services Department, and Mr. Clair D. Darrow was transferred to the  !

Station Training Department. j G. TRAINING During July, Station Training continued technical staff and managerial personnel training. The hot license class attended simulator training at Combustion Engineering. Licensed operator requalification and equipment operator-nuclear auxiliary building training contiriued during the month.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT 10 10CFR50.59 None '

II. MAINTENANCE (Significant Safety Related)

None.

M M l W. Gary G tes Manager-Fort Calhoun Station i

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Omaha Public Power District 1623 Harnet.J Omaha, Nebraska 68102 402/536 4000 August 13, 1987 LIC-87-569 ,

U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

July Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1), l please find enclosed, one copy of the July 1987 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Sincerely,

/ /46J R. L. Andrews Division Manager Nuclear Production RLA/me Enclosures c

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) 1 1

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