ML20071F518
| ML20071F518 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/09/1978 |
| From: | Hickle B OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20071F516 | List: |
| References | |
| NUDOCS 7810130126 | |
| Download: ML20071F518 (9) | |
Text
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I AVERAGE DAILY UNIT POWER LEVEL j
50-285 DOCKET NO.
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UNIT Fort Calhoun #1 October 9, 1978 DATE
- 3. J. Hickle COMPLETED BY 402-536 kh13 17.LEPHONE t
MO s sentenber, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE PAILY POWER LEVEL (MWe-Net)
(Mvie-NetI 43h.8 h3h.9 g
37 h3h.8 h35.h gg 2
h36.2 h35 0 g,
3 h37.7 h32.9 20 4
h38.5 h32.6 21 5
h39.h h31.5 22 6
h39 5 h30.5
. ~23 7
h39.7 430.4 24 8
h38.6 431.1 25 9
h31.1 h38.0 to 26 h38.2 h30.5 27 1I h30.5 h38.h 12 28 h33.0 h38.0 13 29 432.3 h39.0 34 3,
433.0 15 3t h3h.h g6 INSTRUCT 10NS On this format. list the average daily unit power level in MWe-Net for each day in the reporting inonth. Cornpure to the nearest whole rnegawatt.
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OPERATLNG DATA REPORT 50-285 DOCKET NO.
Jet.ot;er 9, 1978 DATE COMPLETED BY B. J. hickle TELEPHONE h02-536 kh13 OPERATING STATUS Fort Calhoun Station Unit No. 1 Notes
- 1. Unit Name:
- 2. Reporting Period:
Sentenber. lo78
- 3. Licensed Thermal Power IMWtI:
1420 i
502
- 4. Nameplate Rating (Gross MWe):
"5I
- 5. Design Electrical Rating (Net MWe):
"bl
- 6. Maximum Dependable Capacity (Gross MWel:
"SI
- 7. Maximum Dependable Capacity (Net MWel:
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Sinte Last Report. Give Reasons:
N/A N/A
- 9. Power Level To which Restricted. If Anj Net MWe):
- 10. Reasons For Restrictions. If Any:
This Month Yr.-to-Date Cumulatise 720.0 6,551.0 h3,968.0
- 11. Ho:sts in Reporting Period
- 12. Number Of Hours Reactor Was Critical 720.0 6,114.4 35,377.7 0.0 0.0 1,136.0
- 13. Reactor Reserve Shutdown Hours
- 14. Ilours Generator On.Line 720.0 6,088.5 34,572.4
- 15. Unit Resene Shutdown Hours 0.0 0.0 0.0 1,011,328.4 8,451,953.9 41,114,476.2
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH) 329,508.0 _,
2.821,293.7 13,626,631.7 IS. Net Electrical Energy Generated (MWH) 313,192.8 2,682,629.5 12,854,598.5 100.0 92.9 To.6
- 19. Unit Senice Factor 100.0 92.9 78.6
- 20. Unit Availability Factor 95.2 o9 7 o4.o
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 95.2 69.6 64.0 0.0 4.1 5.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:
Refuelinc Outace, October 15, 8 weeks t
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION (9/77 )
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Refueling Information Pbrt Calhoun - Unit No. 1 Report for the nonth ending Sept. 30. 1978.
1.
Scheduled date for next refueling shutdown.
October 15, 1978
~~
2.
Scheduled date for restart following refueling.
December 1,1978
~
- 3..Will refueling or resumption of operation thereafter require a technical specification change or other Yes license amendment?
If answer is yes, what, in general, will a.
these be?
Technical Specifications changes with reload i_
application submitted to NRC on August 4,1978.
b.
If anser is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ccanittee to deter-mine whether any unreviewed safety questions are associated with the core reload.
If no such review has taken place, when is c.
it scheduled?
4.
Scheduled date(s) for submitting proposed licensing Submitted Aug. 4, 1978 action and support information.
5.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis nothods, significant changes in fuel design, new operating procedures.
6.
We number of fuel asse:rblies: a) in the core 133 assemblies b) in the spent fuel pool 113 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483 7.
%e projected date of the last refueling that can be discharged to the spent fuel pool assuming the present 1985 licensed capacity.
Prepared by 4
Date October 2, 1978 5
OMAHA PU3LIC PC'4ER DIS 3IC" Fort Calhoun Station Unit No. 1 September 1978 Monthly Cperations Report I.
OPERA"IOUS SLTARY During the month of Septe=ber, installation of the security syste: =cdifications continued. Waste solidification syste modifications are essentially ec=plete. Preoperational checkout of individual vaste system ec=ponents has been initiated. Unit operations continued at near reated capacity throughout the month.
Maintenance on A condensate pump is continuing. Refueling cutage preparations continued. FCS Unit is scheduled to be shutdevn the evening of Friday, October 13, 1978, for the fall refueling outage.
Extensive preventative =aintenance en the vaste evaporator was conpleted. This should provide for optimum performance of the evaporator during the cutage.
Operations personnel identified a reactor coolant syste leak on sampling root valve (RC-138) packing. RC-138 was shut to ter-minate the leak.
A.
PERF0EMA7CE CHAPACTERISTICS LER Number Deficienev 78-026 Rev. 1 During normal steady state power operation, "3" channel RPS variable overpower trip reset de=and alar = actuated and would not reset. Shcrtly after this alam came in, the High power and the=al mar-gin / low pressure trip units for "3" channel PSS failed to the tripped condition. The three re=ain-ing RPS channels remained operable throughout this event.76-027 During the perfc= ance of Surveillance Test ST-ESF-5, Section F.1, the monthly AC sequencer timer test, ti=er SI-13 on sequencer S2-2 failed to time out within the prescribed li=it.
The ti=er was exercised and tested within specified
'4-4 s.78-028 During the ec=pilation and review of veather data for the first 1978 se=1-annual report, historically censi:: tent vind stability classes could not be detemined due to a failure of the Tri-X veather tover's 100 meter Delta-T senser system between March 14, 1976 and July 21, 1978.
Inability te report stability class infom atien is not in ec=-
liance with USURC Regulatcry Guide 21.
Monthly Operations Report September 1978 Page Two A.
PERFORMANCE CHARACTERISTICS (Continued)
LER Nu=ber Deficiency 78-029 Inadvertent radioactive gas release to the atmosphere occurred due to leakage from the chemical volume control tank through check valves CH-28h and HG-100 and relief valve HG-105. Operations noted gradual decrease in tank pressure and initiated action to gas relief valve HG-105 and isolate HG-105 with valve HG-101. Releases were within Technical Specificiation Limits.78-030 While performing an operability check after preventive maintenance on the auxiliary steam driven feed pump, the steam inlet valve YCV-10h5 did not open. The instrument air supply to YCV 10h5 was found to be closed and YCV-10h5 was ir its failed closed position. Manual operator action vould have been required to start FW-10.
3.
CHANGE 3 IN OPERATING METHC]S None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIO'IS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix 3, vere perfor=ed in accordance with the annw'. surveillance test schedule. The following is a su= mary o'. the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:
Operations Incident #
Deficiency OI-650 While performing ST-FD-1, 13 fire detectors in Zone 13 vere found out of calibration. Although cut of calibration, the detectors were operable and were recalibrated to vithin specification.
The following is a surveillance test where an unusual result occurred:
1 Surveillance Test No.
Descrintion ST-CONT-2 P.A.L. door test failed.
Monthly Operations Report September 1978 Page Three D.
CHANGES, TESTS AND EXPERIME:iTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descriution DCR 77-Sh Seismic supports installed per design package on Rav Water, Component Cooling, Chemical and Volume Control and Blowdown systems to alleviate possible over stress conditions on pipe supports in those systems.
SP-FAUD-1 Fuel Assembly Uplift Condition Detector. All g
loops show greater that 99". assurance that greater than 150 lbs downward force exists in the fuel assemblies.
SP-RPS-5 Excore Detector Symmetric Offset Recalibration.
The upper and lover excore subchannels were ad-justed as necessary to conform with actual power tilts in the core as determined by the incere detectors.
ST-WDS-8 Waste Evaporator Chemical Flush.
ST-CONT-2 Personnel Air Lock (PAL) 0-Ring Seal Test.
Daily results are acceptable.
E.
RESULTS OF LEAK RATE TESTS
(
All RCS leak rate results in spec.
Co=pleted leak rate tests on penetrations M-87 and M-88.
Results satisfactory.
ST-CONT-2.- PAL door test failed. Retest after =aintenance was satisfactory.
F.
CEANGES IN PLANT OPERATING STAFF Mr. Kenneth Stier was employed as an Auxiliary Operator-Nuclear.
G.
TRAINING Hot license training was increased for three candidates that are preparing for NRC exams. Tvc candidates are upgrading their licenses frcn RO to SRO and one candidate is seeking a 30 license.
Nomal plant training continued for Maintenance Group such as Crane Operator requalification and Security and Radiation Pro-testion Refresher.
9 Monthly Operations Report September 1978 Page Four H.
CHANGES, TESTS AND EXPERIEMNTS REQUIRING NUCLEAR REGUIATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59 Changes.to' Operating License DPR-ho Amendment No. 40 dated August 23, 1978.
a.
Section 3.15 revised to specify fire pump strainer surveillance and revised fire detector inspection frequency for detectors which would require off-nomal equipment alig=ent.
b.
Modifications designated in NRC safety evaluation report for fire protection program at Fort Calhoun Station made condition of operating license. All September 1978 fire protection implementation con:mittment ite=s vere conpleted this month.
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Approved by Manager-Fort Calhoun Staoion N
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.V.cntQ Operations Repc..
Septe=ber 1978
?nse yire 1!.
MC.. aA ICI (Sienificant Safety Related)
M. O. O i
Date i
Descristien i
Cer ective Action 19880 8-28-78 Check ref legs for SI-6A, 3, C, D Reference legs filled and level trans=itters returned to service.
199h3 9-5-78 CH-13 change cil.
Cc=pleted.
19923 9-1-78 FP-156, FP-158 check for leakage changed rubber seats.
19920 9-1-78 FF-311 flushing valve bonnet broken Replaced.
19939 9-3-78 CH-1A p=p showed loss of flow with Repaired pu=p erratic a=ps.
199s 8-30-78 RPS channel "B" VHPT operating Replaced + 18 volt power supply erratica.lly.
20007 9-13-78 FF-156 vill not close.
Replaced pin and retunned te nor'" A '.
19851 9-12-78 Test spare R.C. pu.p seal lever Pressure breakdown device tested pressure device.
satisfacterily in accordance with PRC approved precetre.
20032 9-16-78 CH-1A leaks Repacked pu=p and replaced all cap gaskets.
20070 9-21-78 Preventive Maintenance on Auxiliary Changed cil in Auxiliary Feed Feed Punp (Ta'-10)
P=p ( 74-10 )
20C.
9-15-78 CH-13 packing cccling pu=p I=peller set screw replaced.
201k0 9-28-78 PAL Door failed test.
Fluffed seal.
2002L 9-28-78 Fire Protection 5.I.R. Septenber 1978 Cc=pleted.
20059 i=ple=entatic ite=s 20078
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