ML20042E060

Monthly Operating Rept for Mar 1990 for Fort Calhoun Unit 1. W/900416 Ltr

ML20042E060
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1990
From:	Gates W, Stice D OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0316, LIC-90-316, NUDOCS 9004190251
Download: ML20042E060 (8)

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Omaha Public Power District' 1623 Harney Omaha, Nebraska 68102 2247 April 16, 1990 402/536 4000

-LIC-90-0316 <

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington,'DC 20555

References:

1. Docket No. 50-285

2. Lotter from NRC (L. M. Muntzing) to OPPD (T. E. Short) dated September 22, 1977 Gentlemen:

SUBJECT:

March Monthly Operating Report (MOR) e Pursuant to Technical Specification Section 5.9;1, and 10_CFR Part 50.4(b)(1), ,

E please find enclosed one copy of the March 1990 Monthly Operating Report for ~

l the Fort Calhoun Station Unit No. 1.

i In accordance with' Reference 2, Omaha Public Power District-(0 PPD) includes a - 1 summary. of major safety-relt'M maintenance as part of'the MOR. In recent MORs, OPPD has provided a- coi:# uter printout of. maintenance data 'as an attachment to the report. Since'a description of significant safety-related maintenance is included in the Operations. Summary, these maintenance printouts are not considered necessary and will no. longer be included in the MOR.-

L If you should-have any questions, please contact me.

j . Sincerely, i

f, i

W.'G. Gates Division Manager Nuclear Operations L WGG/pjc

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h c: LeBoeuf, Lamb, Leiby & Ma'cRae .

!- R. D.-Martin, NRC Regional Administrator,. Region IV P. H. Harrell, NRC Senior Resident Inspector

R. M, Caruso . Combustion Engineering

' . R. J. Simon - Westinghouse' Office of Management & Program Analysis (2)

. Nuclear Safety Analysis Center .,

INP0 Records Center American Nuclear-Insurers 900419025i 900331 ~;f .I r[. PDR ADOCK'05000285 .

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AVERAGE DAILY' UNIT POWER. LEVEL DOCKET NO.~- 50-285-UNIT-  : Fort Calhoun Station- .

DATE' April-12, 1990 l COMPLETED BY D. L. Stice l TELEPHONE (402)636-2474 ]-

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MONTH-' March 1990

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- DAY - AVERAGE DAILY. POWER LEVEL ' DAY-- AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1- 0- 17-. - _ 0L 'j-2 0 18- 0 i 3 0' 19 0 4 0 20 0- l 5 0 21 0 6- -0 22 0' 7 0 23 >0'  !

8 0 24 -04 9 -0 ~ 25 0  ;

10 0 26 0'

11 12 0

0 27 ~ 0- j 'l 28 0- i 13 0 29. 0-14 0 30 - 15~ 0 31 0 i 16 0-

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INSTRUCTIONS On this form, list the-average daily unit power level in MWe-Net for each day '

in the reporting month, Compute to the newest whole megawatt.

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OPERATING DATA REPORTL 1

DOCKET NO. 502285 UNIT ' Fort Calhoun-Station DATE~ April 12, 1990 COMPLETED BY D. L. Stice TELEPHONE (402)636-2474

.0PERATING STATUS-j

1. Unit Name: Fort Calhoun Station- Notes'

' 2. Reporting Period: March =1990  ;

3;. Licensed Thermal Power (MWt):- 1500

4. NameplateRating(GrossMWe):= 502-

5. DesignElectricalRating(NetMWe): 478

6. Maximum Dependable Capacity (Gross MWe):- 502

'7.- 478--

8. Maximum Dependable If changes occur inLCapacity Capacity Ratings(Net MWe)(: .

ItemNumbers3through7)Since:LastReport, i

Give Reasons:-

N/A i

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

110. Reasons for Restrictions, If Any:

N/A l N/A -i

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This Month; Yr-to-Date- Cumulative

11. Hours in Reporting Period 744.0- 2,160.0 144,770.0

12. Number of-Hours Reactor was Critical- 0.0 1,142.1- 112,308.4- <

13. Reactor Reserve-Shutdown Hours 0.0 0.0 1,309.5: i

14. Hours Generator On-Line- 0.0' 1,130.6~ 111,136.0 1

15. Unit Reserve: Shutdown Hours 0.0 0.0 0.0 1

16. GrossThermal.EnergyGenerated(MW 0.0- A 675,900.7 145,291,011.9 17.- Gross Electrical: Energy Generated- WH). 0.0 646,866.0 47,756,974.2

18. Net Electrical Energy Generated (M ) l 0.0 521,906.2 45,589,459.0

19. Unit Service Factor -0.0- 52.3 76.8

20. Unit: Availability Factor 0.0 52.3- 76.8

21. UnitCapacityl Factor (UsingMDCNet) 0.0 - 50.5 68.4

22. . Unit Capacity Factor (Using DER Net) 0.0 50.5 66.8 q

-23. Unit Forced Outage: Rate. 0.0 -0.0- 2.9

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

The~12th-Refuelino Outage commenced on February 17, 1990 with startup scheduled for May 13, 1990.  !

'25. If Shut.Down-at End of Repcrt Period, Estimated Date of.Startup: May 13, 1990-

26. Units.In Test-State d'

'rior to Commercial Operation): Forcast. Achieved.

INITIAL CRITICALITY  ;

-INITIAL ELECTRICITY N/A  ;

COMMERCIAL OPERATION a

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~. Refueling Information

.- Fort Calhoun - Unit No. 1 -I Report-for the month ending -March 1990 i

1. . Scheduled date'for next refueling-shutdown. February' 17. 1990

2. Scheduled date for restatt following refueling. May 13. 1990

-3. Will refueling or resumption of operation thereafter-require a technical specification change or other license amendment? Yes

a. If anbwer is.yes, what, in general, will these be?

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1) Decrease-the total unrodded integrated j radial peaking factor-from 1.80 to 1.70. ,

2) Decrease-the total unrodded planar radial .l peaking' factor from l'.80 to 1.75. J

3) Decrease the PLHGR- from 15.22 to 14.4 Kw/f t .  !

4) Change the TM/LP Pvar equation to reflect a change in the gamma term from -11350 to -11240,

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. N/A

c. If no such review has taken place, when is it scheduled? N/A l

4. Scheduled date(s) for submitting proposed licensing .j action and support information. Submitted Jan. 1990  ;

5. .

Important licensing considerations associated with refueling, e.g., new or differ 6nt fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new '

I operating procedures. None- '

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 ein consolidation or dry cask'stcrage

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7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present' licensed espacity. 1994*  ;

• Capability of full core offload of 133 assemblies lost.

i Prepared by M nit-W Date April 11. 1990

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DOCKET NO. 50-285

~  : UNIT MAPE Fort Calhoun _ Station DATE April 12, 1990 UNIT SHUTDOWNS AND POWER REDUCTICKS COMPLETED BY D. L. Stice TELEPHONE (402) 636-2474 REPORT MONTH March,1990

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cause a correcttve .

No. Date .. i5 -8 iEg Event s fg ' Action to k 3$ h] Report e Prevent Recurrence a

90-01 900217 S 1029.4 C 1 N/A XX XXXXXX On February 17, 1990, the 12th

- Fort Calhoun Station Refue!!ng Outage commenced.

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3 4 1 2 heethod Exhtdt G - hetructions F-Forced Reasort t4denuel for Properation of Data S-Sche &ded . A-Equipment Fagure (Exgdeln) 2-Manuel Scrarn .! Entry Sheets for Ucensee B-Malntenance or Test '

3-Automatic Scram Event Report (LER) F5e 1NUREG-0164 -

C-Refueeno -

4-Other (Expimin)

DA* tory Restriction '

E-Operator Training & License Examination 5 ExNtdt 1 - Some Sevee :

F-Administative -

G-Operational Error -

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H-Other (Explain) -

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4 OMAHA PUBLICIPOWER DISTRICT Fort Calhoun Station Unit No. 1 March 1990 Monthly Operating Report I. OPERATIONS

SUMMARY

Fort Calhoun Station continued with its twelfth refueling and maintenance i outage. The 60 PSIG_ Integrated Leak Rate Test (ILRT) was performed:on the- _l containment structure. Individual penetration leak rate testing continued -!'

through the month. Outages'for trip testing and preventive maintenance-were. conducted on 161 KV offsite power, two inhouse 4160 V buses, and -

T severet 480 V buses. The #1 battery discharge test was performed e The~  !

annual inspection on emergency diesel generator DG-1 is complete and it was  ;

returned to service.-

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The reactor vessel head was removed and the core was off-loaded to the' .i spent fuel pool where all Control Element Assembly (CEA) and neutron source i moves were completed. A temporary spent fuel pool cooling system was placed in service using chiller units to cool- the pool'. _ With this temporary cooling system in service, the component cooling! water system and the raw water system were removed from service and drained for extensive maintenance.

Inspection of-the reactor coolant pump bearings found that all four upper.

guide bearings showed signs of excessive wear. The bearings are being rebuilt. Eddy current testing (ECT) of the U-tubes in both steam generators indicated no tubes required plugging.- ECT was- also- conducted on i "A" condenser- and several feedwater< heaters. Motor operated valve j apparatus testing (MOVAT), modifications.and preventive maintenance are l being performed on_ motor operated valves. The primary water storage tank 1 interior was stripped, repaired and repainted. 'The turbine generator.high  !

pressure rotor first stage ~ blading has been replaced. >The. retaining rings i' were replaced on the main generator.

The following modifications are in progress: DC sequencer replacement; l control room indication for' diesel generator malfunction; redundant power supply for raw water / component cooling interface valves;. increasing the minimum flow of the main feedwater pumps; replacement of area radiation- i monitors; redistribution of loads on the DC buses andsinverters; replacement of valves; control room heating, ventilation, and air conditioning ~(HVAE) habitability' upgrade; containment equipment hatch crane; addition of third auxiliary feedwater pump; RCS narrow range mid-loop level indication;1 steam generator _ blowdown tank erosion; feedwater regulating valve supports; alternate shutdown panel wiring for fire protection; and, limitorque valve operator tharmal: overload bypasses, q i

The following modifications for control room design review for human factors are in progress: reactor regulating system / steam dump and bypass  ;

alarms; meter scales; replacement of oddly shaped switch handles; labeling, demarcation, and meter banding.

A review of all large bore Critical Quality Element piping for Thermal Anchor Motion, nozzel loadings, Seismic Anchor M Eion, and zero period

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Monthly Operations Report Page Two d

acceleration consideration determined the following:  !

Steam generator-blowdown piping-near the steam generator had an overstress condition due to thermal growth of the generators. Nineteen supports on the main steam piping in containment and safety. injection piping were  ;

~found to exceed theit' design capacity. Modifications have been initiated :i to resolve the_ concerns. The sup) orts on'the main steam piping outside containment cannot adequately witistand seismic.and safety relief valve.

discharge loadings. Failure of these supports would. create overstress 1 conditions'in the-main. steam-piping.

An analysis showed that_in the ev9nt of-a main steam line break inside 4 containment,_ the pressure in the auxiliary feedwater piping between each ,

pair of the containment penetration isolation valves would exceed design  !

limits. The resolution of this issue is to be addressed in upcoming 1 Licensee Event Report 90-009. '

-The following NRC inspections took place in March: 1 IR 90-04 System Entry and' Retest (SERT) Team Inspection IR 90-07 Technical Specifications Calibration Verification-IR 90-09 ILRT Program _

IR 90-10 Compliance with: Appendix J Local 1 Leak Rate Test (LLRT)-

Requirements ,

IR 90-10 Residents' Monthly Inspection (to continue through April 14, t 1990) 'I IR 90-14 Procedures Prcgram IR 90-15 Intervice Inspection (ISI) and Snubber. Program IR 90-16 Welding Program:

IR 90-17 Maintenance & Test Equipment (M & TE) Program IR 90-18 Outage Occuphtional ' Exposure IR 90-19 Environmental- Monitoring Program IR 96 ?.1 Special - Loss of Off-site Power j t

IR 90-22 ISI Data and Records

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The following LERs were submitted: Date Submitted 89-024R1 Containment Spray Piping.0utside Design Basis ' March 30,L1990 90-002 Inadvertent Actuation of Containment March 28, 1990 Isolation Actuation Signal. 'l 90-003 Auxiliary Feedwater Piping Outside Deshn- March 19,(1990 Basis Due to~ Design = Deficiency 90-004 1

Main Steam Safety Valves Outside Setpoint March 19,1990 : i

. Acceptance Criteria- '90-005 Spent Fuel Pool Ventilation System Outside March 26, 1990 Design Basis 90-006- Loss .of Off-Site Power end Diesel Generator March 28,'i990 Actuatior. ,90-007 Main Feedwater Piping outside Design Basis March 30,~1990 i I

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4 Honthly Operations Report Page Three '-

i A. SAFETY VALVES OR PORY CHALLENGES'OR FAILURES WHICH OCCURRED  !

l No PORV or Safety Valve challenges or failures occurred.

B. RESULTS OF LEAK RATE TESTS  !

During the month of March 1990, the reactor was in refueling shutdown l condition (Mode 5). Therefore, the Reactor CoolantLSystem Leak Rate l test, ST-RLT-3 F.1,;was not performed.

C. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR-REGULATORY COMMISSION AUTHORIZATION PURSbviT TO 10CFR50.59 j

Amendment No. Descriotion No. 125 This amendment changes the Fort Calhoun Technical  !

Specification to' place- operability and-surveillance requirements on the alternate shutdown panels AI-279,'185, and 212. These 1 Technical Specification changes include additions i to section 2.15,. Limiting Conditions for Operation l (LCO) and Table 3-3a. 1 II.. MAINTENANCE (Significant Safety Related)

See Section 1 Operations Summary Gary R. Peterson Manager-Fort Calhoun Station h

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