ML20080H020

Monthly Operating Rept for Aug 1983

ML20080H020
Person / Time
Site:	Fort Calhoun
Issue date:	09/12/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8309200420
Download: ML20080H020 (10)

Text

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, AVERAGE DAILY UNIT POWER LEVEL o

f DOCKET NO. 50-285 UNIT Fort Calhoun Statio-DATE Seoteraber 12, 1983 COMPLETED BY T. P. flatthews TELEPHONE (402)S36-4733 MONTH Aut,ust, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) t MWe-Net) 440.8 i7 436.7 2 439.8 is 436.2 3 441.2 39 437.2 4 441.1 20 438.2 5 ,

438.9 2: 439.0 6 437.9 22 438.7 7 437.7 23 439.9 g _

437.F 24 439.6 9 436.4 25 439.7 to 436.7 26 440.3 II 437.9 27 414.4 12 440.4 23 266.6 13 440.8 ,, 437.9 34 440.8 438.3 39 15 .

439.7 3, 439.4__

16 437.8 i

INSTRUCTIONS On this format. list the average daily unit power leselin MWe Net for each day in the reportmg ini.uth. Cuenpute to the nearest whole megawatt.

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8309200420 830912

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE September 12, 1983 COMPLETED llY T. P. Matthews TELEPil0NE (402)5'36-4733 OPERATING STATUS N"

1. Unit Name: Fort Calhoun Station

2. Reporting Period: August, 1983

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

4. Nameplate Rating (Gross MWe): 501 4/6

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): 461

7. Mas l mum Dependable Capacity (Net MWe): 438

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

The first stage blading of the hiah pressure turbine was ronnved aftor a failure of that blading in December of 1982 and temporarily replaced with a pressure plate prior to startup followig

9. Power Lesel To Which Restricted.lf Any(Net MWep: N the 1983 refueling outage.

10. Rea ons For Restrictions.If Any: None This Month Yr. to Date Cumulatise

11. Hours in Reporting Period 744.0 5,832.0 87,073.0

12. Number Of Hours Reactor Was Critical 744.0 3,574.9 66,964.9

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.5

14. Hours Generator On-Line 744.0 3.476.0 66.473.5

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWHI 1,096,899.4 4.825,058.0 82,440,606.4

17. Gross Electrical Energy Generated (MWil, 338,624.0 1,511,476.0 26.934.95_525

18. Net Electrical Energy Generated (MWHI 321,777.2 1,433,408.5 25,763,442.9

19. Unit Senice Factor 100.0 53.7 76.1

20. Unit Availability Factor 100.0 53.7 76.1

21. Unit Capacity Factor (Using MDC Neti 98.7 56.1 64.1 l

22. Unit Capacity Factor (Using DER Net) 90.5 51.4 62.2 l 23. Unit Forced Outage Rate 0.0 1.4 3.8

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

1984 refueling outage scheduled to start around March 16. 1qM and last for approximately two months.

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICI FY COMM ERCIAL OPER A TION i

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DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUC 110NS UNIT NAME fort Calhoun Station DATE SeDtember 12. 1983 COMPLETED BY T- P _ fla tthowc REPORT MONTH Auqust. 1983 ( 40? M1Fi-4711 TELEPHONE w.

- E c

, ' E_ g 3 j E3 Licensee ,En, ja, Cause & Corrective No. Date i 3g 7, 2ss Event g? g3 Action to H y: 5 }gg Report a mO g

O Prevent Recurrence d

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

i 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) l-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report iLER) File INtlR1 G.

D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination ,

F.Administ ralise 5 G-Operational Error (Explam) Exlubit I - Same Source (9/77) Il-Other (E xplain) 1

Refueling Information Fort Calhoun - Unit No. 1 Report for the nonth ending Auaust 1983 .

l. Scheduled date for next refueling shutdown. Ma ,.c h 19M

2. Scheduled date for restart following refueling. May 1984

3. Will refueling or resumption of operation thereafter require a tecimical specification change or other.

license amendment? Yes

a. If answer 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 Ccemittee to deter-

.mine whether arrf 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 198:

action and support information. Tech. Specs. - Feb.ruary 1984

5. Inportant 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.

6. The number of fuel assemblies: a) in the core - 133 assemblies b) in the spent fuel pool 265 c) spent fuel pool storage capacit'/ 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 Q/ September 1, 1983

-Prepared by- /

htJA Date y< v

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 August, 1983 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power through the month until August 27, 1983. Power was reduced to 40% for repairs to a condenser valve. Power level was returned to 100% August 28, 1983.

Twenty-one spent fuel pins used for the DOE extended burnup study were returned to the site.

Four operators and two engineers took the NRC Senior Reactor Operator examination.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency 82-019 On October 24, 1982, at approximately 1624, while the plant was in a cold shutdown condition, the Main Steam Isolation Valves, HCV-1041A and HCV-1042A, were sig-naled to close by the plant operators; however, the valves stopped closing three to four degrees off their seat. Investigation into the problem revealed that binding between the valve packing and shaft precluded full closure.83-004 During performance of surveillance test ST-ESF-3 F.2,

" Containment Pressure Channel Check", pressure switches A/PC-742-1 and A/PC-742-2 were found to be initiating / actuating above the Tech. Spec. limit of 5 psig. During the time pressure switches A/PC-742-1 and A/PC-742-2 were considered inoperable, the

! remaining pressure switches feeding the B, C and D channels of "A" and "B" Containment Pressure High Signal initiation matrices were operable, available and fully capable of initiating protective actions required to mitigate the consequences of an accident.83-006 During routine plant operations at approximately 100%

power, the "D" Reactor Protective System (RPS) channel

" Axial Shape Index internal tilt" pretrip setpoint was found to have drifted out of specification tolerance i

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-Monthly Operations Report

. August, 1983 Pa'ge Two LER Number De_ficiency 83-006 (continued) in the non-conservative direction during performance of surveillance test ST-RPS-12 F.2, " Axial Power Distribution Channels Test". The "0" channel of the RDS for Axial Power Distribution was immediately placed in bypass. During the time when "D" chanr.el was bypassed, the remaining "A", "B" and "C" Axial Power Distribution Channels of the RPS were operable, available and capable of providing reactor trip if required to do so.

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 01-1744 ST-CHEM-1 F.3 Steam generator blowdown and monitor tank releases Strontium 89 and 90 MDA's did not meet the sensitivity requirements.

01-1745 ST-RM-2 F.2 Plant containment air particulate monitor RM-051 alert setpoint out of specification.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT. COMMISSION APPROVAL System Acceptance Committee Packages for August,1983:

Package Description / Analysis EEAR FC-79-72 Seismic Support FWS-83 Located in Room 81.

This modification installed a support on FWS-3 l located in Room 81. This modification has no L adverse effect on the safety analysis.

l G.

Monthly Operations Report Augus t,1983 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Package Description / Analysis EEAR FC-80-39 Concentrate Tank Drain Line.

This modification replaced a carbon steel drain line with a stainless steel drain line. This modification has no adverse effect on the safety analysis.

EEAR FC-81-118 Emergency Preparedness-Emergency Response Facility Communication.

This modification installed facsimile trans-mission equipment at the Fort Calhoun Station.

This modification has no adverse effect on the safety analysis.

DCR 76-57 Replacement of Raw Water Pump Snubbers (AC-10Donly).

This modification replaced existing raw water pump snubbers (AC-10D only). This modification has no adverse effect on the safety analysis.

DCR 78-23 Sample Valve on Turbine Oil Tank L01.

This modification provided an easier method of obtaining turbine oil samples from a non-safety related system. This modification has no effect on the safety analysis.

EEAR FC-78-61 Component Cooling Safety Valves.

This modification changed the set pressure of component cooling safety valves. This modifica-tion has no adverse effect on the safety analysis.

EEAR FC-79-97 Evaluation of Raw Water and Feedwater Pipe Supports.

This modification repaired defective supports.

This modification has no adverse effect on the safety analysis.

E. RESULTS OF LEAX RATE TESTS There are no new leak rate results to report.

' Monthly Operations Report

. August, 1983 Pa'ge Four F. CHANGES IN PLANT OPERATING STAFF During the month of August the following changes in Plant Operating Staff occurred:

John Riley, Shift Supervisor, retired August 1,1983.

Gary Peterson, Supervisor-Maintenance, resigned August 15, 1983.

Merl Core, Supervisor-Instrument and Control and Electrical Field Maintenance, was promoted to Supervisor-Maintenance August 16, 1983.

Randy Mueller, Instrument and Control Engineer, became the Acting Supervisor-Instrument and Control and Electrical Field Maintenance August 16, 1983.

Jerry McMahon, Equipment Operator-Nuclear License, resigned August 26, 1983.

G. TRAINING General employee training was conducted as scheduled. Operations received training in thermodynamics, fluid flow, hydrostatics, emergency procedures and fire brigade. Maintenance received sys-tems training. Chemical and Radiation Protection personnel received' scheduled requalification training. Chemical and Radi-ation Protection Trainees received initial training on systems, counting lab, offsite monitor, emergency response plan procedures and dose calculations. Six candidates sat for the NRC administered SR0 examination and oral walkthrough.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

M 0. # DATE DESCRIPTION ,

CORRECTIVE ACTION 18079 2/10/83 Replace sample line valve on Completed.

safety injection tank B.

18077 2/26/83 Penetration M-42 leaking. Replaced bad parts and retested per ST-CONT-3.

18071 3/29/83 Wide range "B" not working. Recalibrated.

18054 2/11/83 DG-2 will not start unless Cleaned valve and reinstalled.

being primed.

Monthly Op: rations Report August, 1983 Page Five II. MAINTENANCE (Significant Safety Related) (continued)

M.0. # .DATE DESCRIPTION CORRECTIVE ACTION 20968 7/23/83 Leak check RM-50/51. Found leak on fitting and repaired.

21104 7/21/83 RM-50/51 leaks. Repaired valve.

21160 7/29/83 PAL seal failed test. Installed new seals in inner door.

12662 11/9/81 CRHS 86 relay on AI-30B did Replaced burnt up coil and cleaned not trip. up mechanical latch. Replaced blown fuse.

21044 2/14/E3 Internal ASI APD internal tilt Replaced module A-1.

out of tolerance.

21116 7/29/83 RPS "B" channel position ASI Replaced DEVAR module.

reading 1800 where others are reading 1300.

21317 8/6/83 RPS M-1 "M" coil power has Replaced one IR-1 relay and six failed. matrix relays.

W_ # 7t2D W. Gary Gates Manager Fort Calhoun Station

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 September 15, 1983 LIC-83-239 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 August Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely,

, O W. C.iJones Divie ion Manager Production Operations WCJ/TPM:jmm Enclosure 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 I i 1

45.5124 Employment with Equal Opportunity MalelFemale

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