ML20076L395

Monthly Operating Rept for June 1983

ML20076L395
Person / Time
Site:	Fort Calhoun
Issue date:	07/14/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-172, NUDOCS 8307190158
Download: ML20076L395 (10)

Text

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, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Statior DATE July 14, 1983 COMPLETED BY T. P. Matthews TELEPilONE (402)536-4733 MONTM June, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) lMWe-NetI i 455.1 i7 452.5 2 457.4 i3 453.1 3 455.1 19 453.2 4 457.2 20 452.1 5 458.5 21 450.3 6 458.4 447.1 22 7 458.5 444.6 23 8 457.3 24 443.0 9 455.6 442.1 25 to 454.5 441 4 26 i 454.8 441 9 27 12 454.3 445.1 23 13 454.7 29 447.9 14 454.8 30 449.6 is 453.9 33 is 451.5 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe Net f or each day in the repinting inimth.nimpute to the nearest whole megawati.

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE duly 14, 1983 COMPLETED liY T. P. fiatthews TELEPilONE - (402 M36-4733 OPERATING STATUS

1. Unit Name: Fort Calhoun Station N"

2. Reporting Period: June, 1983

3. Licensed Thermal Power IMW ): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 470

6. Masimum Dependable Capacity (Gross MWe): 501

7. Masimum Dependable Capacity (Net MWe): 478

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Gise Reawns:

N/A '

9. Power Lesel To which Restricted,if AnyINet MWe): N/A

10. Reasons For Restrictions. If Any: None This Month Yr..to.Date Cumulatise -

l1. Ilours In Reporting Period 720.0 4,344.0 85,585.0

12. Number Of floun Reactor Was Critical 720.0 2,086.9 65,476.9

13. Reactor Rewne Shutdown llours 0.0 0.0 1,309.5

14. Ilours Generator On.Line 720.0 1,988.0- 64,985.5

15. Unit Rewne Shutdown Hours 0.0 0.0 n.n

16. Grow 1hermal Energy Generated (MWil) 1,074,483.9 2.617.109.8 80.233.658.2 17 Grow Electrical Energy Generated (MWil) 341,628.0.. 826,160.0 26,249.619.,1

18. Net Electrical Energy Generated IMWil) 325, W .7 _ 781,857.8 25,111,892.2

19. Unit Senice Factor 100.0 45.8 75.9

20. Unit Asailability Factor 100.0 45.8 94.5 75J

21. Unit Capacity Factor (Uning MDC Net) 37.7 63.6 i

22. Unit Capacity factor IUsing DER Nel) __

94.5 37.7 61.8

23. Unit Forced Outage Rate 0.0 2.0 3.1

24. Shntdowns Scheduled Oser Nest 6 Months IT> pe. Date,and Duration of Each t:

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

26. Units in Test Status lPrior to Commercial Operation): N/A Forecast Achiesed '

INITIT L CRITICA LIIY INITIAL ELEC1RICITY -

CO\lMERCI \ L OPER \ IlON eni:s

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT N AME DATE Julv 14. 1983 COMPLETED BY T. P. Matthews REPORT MONTH J une,1983 TELEPHONE (4021536-4733

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K g3 Cause & Correctne Action to H y $ j ;f, g Report = mU g' Prevent Recurrence d

9 There were no unit shutdowns for the month of June,1983.

i 2 3 4 F: Forced Reason: Method: Edibit C . Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram- Enta Sheets for 1.ieensee C-Refueling 3-Automatic Scram. Esen't Report (LER) File tNUREG-D-Regulatory Resttietion 4-01her (Explain 1 01oI) 1:-Operator Training & License Examination F Administratise 5 G-Operational Er ror (Esplain) Eshibit I - Same Source 19/77) Il-Ot her ( E splain)

i Refueling Inforration Fort Calhoun - Unit No. 1 Peport for the nonth ending June 1983 .

1. Scheduled date for next refueling shutdown. March 1984

2. Scheduled date for restart following refueling. March 1984

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

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

A Technical Specification Change

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee 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 Methodology - October 1983 action and support information. Tech. Specs. - February 198,

5. Important licensing considerations associated with refueling, e.g. , new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes in fuel design, new operating procedures.

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6. The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool storage capacity - 483 d) planned spent fuel pool storage capacity 728

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 i

l Prepared by /

h4A Date July 1, 1983

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OMAHA PUBLIC POWER DISTRICT

( Fort Calhoun Station Unit No.1 June, 1983 Monthly Operations Report I. OPERATIONS SUl@lARY Fort Calhoun Station operated at 100% power through the entire month of June.

Combustion Engineering has completed the on-site work for the DOE extended burnup study on spent fuel.

' Annual licensed operator requalification training at Combustion Engineering simulator in Windsor, Connecticut, continued through the month of June.

No safety valve or PORV challenges occurred.

A. PERFORf1ANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS

( None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B were performed in accordance with the annual sur-veillance test schedule. The following is a summary of the surveil-lance tests which resulted in Operation Incidents and are not reported elsewhere in the report:

Operation Incident Deficiency 01-1721 ST-FIL-2, F.1 During performance of ST-FIL-2, F.1, VA-26A/B failed the freon removal efficiency test.

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

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.S9 since

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

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. Monthly Operations Report-June, 1983 Page Two

't D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for June,1983:

Package Description / Analysis EEAR/FC-81 -93 Concentrate Pump Change Out (WD-39B).

This modification provides for the replacement of a concentrate pump. This modification has no adverse effect on the safety analysis.

EEAR/FC-81 -148 Modifications to Missile Shield Seismic Supports.

(Phase 1)

This modification provides for the fabrication and placement of 24 removable pins to be used to retain the 12 existing vertical tube posts in their respective tube sockets. This modifi-cation has no adverse effect on the safety analysis.

EEAR/FC-82-166 HCV-321 Seismic Support Snubber Modification.

This modification provides for the installation of rigid struts and U-bolts on seismic restraints

(- for piping to HCV-321. This modification has no adverse effect on the safety analysis.

EEAR/FC-83-42 Bergen-Patterson Pipe Clamp Shear Lugs Modification.

This modification provides for the addition of shear lugs to pipe clamps used in axially loaded seismic restraints. This modification has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS None F. , CHANGES IN PLANT OPERATING STAFF None i

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Monthly Operations Report June, 1983 Page Three G. TRAINING .

Simulator requalification was conducted for NRC licensed personnel at Combustion Engineering's simulator in Windsor, Connecticut. Non-licensed operators received training on systems, classical physics and basic mathematics. Fire brigade training was completed for all brigade members. General employee training was conducted as scheduled.

Maintenance personnel received system lectures. Annual training was given to volunteer fire departments that support the Fort Calhoun Station's operation.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59.

Amendment No. 74 revised heatup and cooldown curves.

II. MAINTENANCE M.0. # DATE DESCRIPTION CORRECTIVE ACTION 18209 1/27/83 Machine and repair "B" steam Machined per procedure.

generator north handhole cover.

5/24/83 LIA-254 level in alarm. Repaired and calibrated sigma.

{20483 18114 3/4/83 CH-14 inspect internals of Completed per procedure.

chemical volume control tank.

18188 3/18/83 MS-291 header flange needs Completed per procedure.

machining.

18187 3/5/83 MS-278 header flange needs Completed per procedure.

machining.

18186 3/5/83 MS-277 header flange needs Completed per procedure.

machining.

18185 3/5/83 MS-276 header flange needs Completed per procedure.

machining.

l 18184 3/5/83 MS-275 header flange needs Completed per procedure.

machining.

18150 2/18/83 CH-4A has seal leakage. Replaced mechanical seal.

18141 3/21/83 HCV-10428 needs repair. Repaired per procedure.

l 18140 3/21/83 HCV-1042A needs repair. Repaired per procedure.

( 18139 3/21/83 HCV-1041B needs repair. Repaired per procedure.

18138 3/21/83 HCV-1041 A needs repair. Repaired per procedure.

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Monthly Operations Report June,1983 Page Four

( II. MAINTENANCE (continued) -

M.0. # DATE DESCRIPTION CORRECTIVE ACTION 18125 2/26/83 CEDM #41 disassemble, inspect, Completed per MP-RC-10-3.

repair.

13282 3/26/83 CB-4 "C" wide range - no Fixed intermitted contacts on SBM indication. switch.

19927 4/21/83 V0PT "D" on CB-4 is stuck. Replaced meter servo motor.

19473 5/4/83 Primary boric acid heat tracing, Repaired circuit P-32.

TAR-2 below or at minimum temperature.

15256 3/23/83 RPS "C" Channel T out of Replaced pot.

calibration. cold 17107 3/19/83 Install new charcoal filter Completed per MP-VA-6-3.

trays in south tank of VA-6A.

17171 1/3/83 Repair HCV-1560A. Completed per approved procedure.

17363 3/15/83 Inspect internals on PCV-210. Replaced internals.

k 20306 5/4/83 RC-133 has broken packing Completed per approved procedure, following stud.

18745 2/22/83 HCV-318 indicates no travel Readjusted and cleaned.

from AI-308.

18695 2/16/83 Agastat 27T1 in 183C is broken. Installed new agastat.

18586 2/22/83 Cable feeding PT-1700 (5941) Cable properly installed.

is out of its tray.

18525 2/5/83 Backflush pressurizer pressure Completed.

reference legs only with D.I.

water.

19058 3/4/83 CCW inlet HCV to SI-2A has a Replaced diaphragm.

. bad diaphragm on regulator.

19017 2/28/83 WD-3A & 3B containment sump Readj usted.

pump control will not start pump in automatic.

19059 3/4/83 FH-12 trolley sticks. Cleaned rails and trolley wheels.

2/9/83 DG-2 governor - make necessary Installed new governor.

(18556 repairs and adjustments.

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.. Monthly Operations Report June, 1983 Page Five II. MAINTENANCE (continued) .

M.0. # DATE DESCRIPTION CORRECTIVE ACTION 19988 5/13/83 Inboard pump seal on SI-3A is Installed new seal and gaskets.

leaking.

19019 3/4/83 FP-6B drain valve leaks by. Installed new valve.

19037 3/3/83 SI-342 leaks by. Replaced bonnet gasket.

19096 3/8/83 FH-4 drive motor erratic. Lubricated contactor and adjusted solenoid relay.

19001 2/24/83 RR099 printing in same spot. Replaced contact brushes.

19181 3/19/83 HCV-484 will not open. Rebuilt 3570 positioner.

19120 3/8/83 Lockout relay 86-2/52-1 bound Replaced coil.

coil.

M/. /2. &

W. G. Gates Manager Fort Calhoun Station

Omana Public Power District 1623 Hamey Omaha, Nebraska 68102 402/536 4000 July 14, 1983 LIC-83-172 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the June Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, ,

l

'. C. Jones Division Manager Production Operations WCJ/TPM:jmm Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center NRC File ZE -24 45 5124 Employment with Equal Opportunity MaleJemale i} l

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