Text

Monthly Operating Rept for Feb 1989 for Fort Calhoun Station Unit 1
	ML20236C061
Person / Time
Site:	Fort Calhoun
Issue date:	02/28/1989
From:	Morris K, Stanley B; OMAHA PUBLIC POWER DISTRICT
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LIC-89-193, NUDOCS 8903210472
	Download: ML20236C061 (19)
	v • d • e

_ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Calhoun Station DATE March 14, 1989 COMPLETED BY B. E. Stanley TELEPHONE 402-636-2456 MONTH February 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1

1 95 17 456 2

106-18 436 i

3 106 19 436

]

4 106 20 436 5

108 21 439 j

6 107 22 461 7

107 23 469 8

119 24 469 9

239 25 470 i

10 275 26 468 11 376 27 468 12 443 28 470 13 450 14 461 15 461 16 461 INSTRUCTIONS y unit power level in MWe-Net for each day On this format, list the average dail.he nearest whole megawatt.

in the reporting month.

Compute to t l

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i OPERATING DATA REPORT DOCKET N0.

50-285 UNIT Fort Calhoun Station DATE March 14, 1989 COMPLETED BY 8. E. Stanley TELEPHONE 402-636-2456 OPERATING STATUS 1.

Unit Name:

Fort Calhoun Station Notes 2.

Reporting Period:

February 1989 3.

Licensed Thermal Power (MWt):

1500 4.

NameplateRating(GrossMWe):

502 5.

Design Electrical Rating (Net MWe):

478 6.

MaximumDependableCapacity(GrossMWe):

502 7.

Maximum Dependable Capacity (Net MWe):

478 8.

IfchangesoccurinCapacityRatings(ItemsNumber3Through7)SinceLastReport, Give Reasons:-

N/A 9.

Power Level to Which Restricted, If Any (Net MWe):

N/A

10. Reasons for Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 672.0 1,416.0 135,266.0

12. Number of Hours Reactor Was Critical 672.0 734.5 104.084.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 672.0 679.2 103.094.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 749,342.5 752.897.8 133.641,891.7

17. Grcss Electrical Energy Generated (MWH) 242,074.0 242,596.0

,43,986.724.2

18. Net Electrical Energy Generated (MWH) 227,964.2 228.080.3 41,999.585.1

19. Unit Service Factor 100.0 48.0 76.2

20. Unit Availability Factor 100.0 48.0 76.2 21 UnitCapacityFactor(UsingMDCNet) 71.0 33.7 67.3

22. Unit Capacity Factor (Using DER Net) 71.0 33.7 65.5

23. Unit Forced Outage Rate 0.0 0.0 2.9 24.

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

None 25.

If Shut Down at End of Report Period, Estimated Date of Startup:

N/A j

26. Units In. Test Status (Prior to Commercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

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Refueling Information Fort Calhoun - Unit No. 1 i

l Report for the month ending February 1989

'1.

Scheduled date for next refueling shutdown.

February 1990 2.

Scheduled date for restart following refueling.

May 1990-3.

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?

- Incorporate specific requirements resulting from reload safety analysis j

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 i

are associated with the core reload.

c.

.If no such review has taken place, when is it scheduled?

4..Scheduleddate(s)forsubmittingproposedlicensing action and support information.

January 1990-5.

Important licensing considerations associated with refueling, e.g., new or different fuel design or 1

supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None Planned 6.

The number of fuel assemblies: a in the core 133 assemblies b in the spent fuel pool 437 c spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel oin consolidation or dry cask storage 7.

The 3rojected date of the last refueling that can be disc 1arged to the spent fuel pool assuming the present licensed capacity.

1994*

Full core offload of 133 assemblies lost.

i Prepared by M'

Date March 13, 1989 l

v; L'

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.'1' February 1989-Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station held at 30% power for steam generator chemical j

contaminant and boric acid soak until February 8.

Power was then l

increased, reaching'98% on February 14, 1989. ~On' February 17, power was-f reduced to 93% to perform moderator temperature coefficient testing.

Power was increased to 100% power on February 22.

During February the NRC performed a welding inspection, an NRC team reviewed-items pertaining-to startup from the refueling outage, a special security inspection was performed by Resident Inspectors, an NRC team reviewed post modification testing, and'an NRC team performed a closeout inspection of old open items.

i On' February 8, 1989, an emergency preparedness drill was conducted.

l Two operators were hired in the Helper classification during February.

One LSO was promoted to Shift Supervisor.

l No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING VETHODS l

Nont C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS l

l None I

l l

p i

1

l Monthly Operations Report-i

' February 1989 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION i

APPROVAL l

SP-ESF-1 1988 Refueling Outage ESF Components Retest l

.l This procedure did not constitute an unreviewed i

safety question as defined by 10CFR50.59 because it verified operability of several components which could not be tested during the normal refueling surveillance due to maintenance activities.

This testing did not in any way compromise plant safety since it ensured

. operability of a number of plant components.

SP-HJTC-1 Electrical Preoperational' Tests This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only measured certain electrical performance characteristics of the Heated Junction Thermocouple (HJTC) probe assemblies prior to their installation into the reactor vessel.

SP-NZ-1 Containment Spray Nozzle Test This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because.

it was written to test 11 nozzles which were not tested during the 1987 refueling outage per l

ST-NZ-1.

The failure to test the nozzles in 1987 resulted in LER 88-008. The successful test of 4

the 11 nozzles completes ST-NZ-1 for 1987.

SP-SI-HPSI High Pressure Safety Injection Loop Injection i

Valve Maximum Differential Pressure Test This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because it was performed to determine if the high pressure safety injection loop valves would function against the maximum expected system differential pressure. The test was written in response to NRC IEB 85-03.

l l'

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l Monthly Operations Report February 1989 j

Page Three SP-SI/CS-2 Performance Data of LPSI, HPSI, and CS Pumps This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because it was performed to record the pump performance data to verify,two points on the characteristic pump curves supplied by the manufacturer.

SP-SI/CS-2 was performed in conjunction with SP-SI/CS-3 in response to a design deficiency

/on,d during a review of NRC IEB 88-04.

SP-SI/CS-3 simultaneous Operation of LPSI and HPSI Puinps in Minimum Recirculation Mode This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because it was performed to determine if the high pressure and low pressure safety injection pumps could run simultaneously in a minimum recirculation mode in response to a design deficiency and pro)osed modification to correct the problem.

T1e design deficiency of the minimum recirculation line was identified during a review of NRC IEB 88-04.

SP-CSF-1 Carbon Steel Fasteners Inservice Testing This procedure did not constitute an unreviewed safety question as defined by 10 CFR 50.59 because h

the test was only a visual inspection for boric acid damage on carbon steel fasteners.

The performance of the inspection has no effect on plant equipment of safety systems.

No degradation of components was discovered and the inspection was completed satisfactorily.

System Acceptance Committee Packages for February 1989:

Packaae Description / Analysis EEAR FC-88-039 SIRWT Bubblers This modification provided for installation of new check valves /NVPRO, test valve connections, isolation valves and new tubing for SIRWT level l

indicators.

The level indicators were function tested for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> holds to prove accumulator operation.

l

Q Monthly Operations Report j

February 1989 Page Four System Acceptance Committee Packages for February 1989:

(Continued)

Packaoe Description / Analysis I

EEAR FC-88-111 Pressurizer Safety Valvr Piping Supports This modification provided for the strengthening of eight supports; BUS-38,. BUS-41, BUS-56, BUS-59, BUS-60, BUS-38 and BUS-70; on the pressurizer relief piping.

This modification was necessary as a result of NUREG-0737.

r..

RESULTS OF LEAK RATE TESTS The reactor coolant system leak rate testing for the month of February 1989 was less than Technical Specification requirements.

Average leak rates were approximately:

0.1 gallon per minute from unknown leak sources.

0.2 gallon per minute from known leak sources.

Total leakage rate approximately.3 gallon per minute.

F.

CHANGES IN PLANT OPERATING STAFF The Operations Department has hired two helpers - Donald Pier and

. Dennis Sloan. Leslie Labs has been promoted to Shift Supervisor.

G.

TRAINING Licensed and Non-licensed Operator Requalification Training was conducted during the month. On February 8, 124 newly developed and 191 previously developed open book exam questions for the licensed operator requalification program were forwarded to the NRC. The A0N-9 class began on February 6 with five students.

One (1) EONT passed his Board in February. Classroom training for the SR0 class continued.

All four (4) candidates 3assed the first three examinations. Maintenance Training 1as set up the labs and sufficient lab equipment is available to conduct hands-on training.

All Maintenance Training instructors are enrolled in OMO courses for 1989.

The Chemistry / Radiation Protection department provided support for RCS access briefings to Fort Calhoun Station and completed training equivalency determinations for 21 new Chemistry and Radiation Protection Technicians.

Equipment is being set up in

Training Center laboratories. Approximately 120 people received General Employee Training during the month of February.

1

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Montnly Operations Report February 1989 Page Five H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. 119 - The amendment modifies the Technical Specifications to (1) change the Safety Injection and Refueling Water Tank minimum temperature, (2) change the title of the Senior Vice President and (3) correct errors in references and a mailing address. Additionally, this amendment revises Facility Operating License No. DPR-40 to delete paragraph 3.0, dealing with the Spent Fuel Pool Modification, since the modification is complete and the applicable Technical Specifications requirements are in effect.

OPPD requested relief from the ASME Section XI Hydrostatic Testing Schedule Requirements for the Class 1, 2, 3 systems that is required by the code at the end of every ten year inspection interval.

OPPD requested that some of the tests be performed at an earlier time in the inspection periods. The relief was requested on the basis that most of these tests be performed in the last inspection period, and the combination of these tests and other major activities required in the last period could result in a long and intensive outage.

The movement of some of these tests to earlier periods would diminish this work load.

The commission reviewed the request and stated that the proposed schedule for the hydrostatic test represents an i

acceptable alternative to the ASME code provided that once a system is tested, it is not changed to a later period in following inspection periods.

II. MAINTENANCE (Significant Safety Related)

See attached printout.

W hs W. Gary Ga es Manager-Fort Calhoun Station 1

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D-l }.....tl};);fQ & )j'f[.,}l*; ; f _; lg llls'* ;J l $ j[ & l. Q.;ll [ O l J).}j'll;

'. ^ :

Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 400C March 15, 1989 LIC-89-193 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

February 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 February 1989 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, h'/

/

l j

?

fffiK.

'J.' Mo)rr i s Division Manager Nuclear Operatior s KJM/bes Enclosures c:

P. H. Harrell - NRC Senior Resident Inspector 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 Ap.erican Nuclear Insurers I

1 I

l l

d'f 45 SIN Employment with Equal Opportunity Male Female I

ML20236C061

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