ML20127C874
| ML20127C874 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/31/1985 |
| From: | Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| LIC-85-255, NUDOCS 8506240037 | |
| Download: ML20127C874 (8) | |
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s AVERAGE DAILY UNIT P0hER LEVEL DOCKET NO.
50-285 Fort Calhoun Station usir une 7, 1985 DATE COMPLETED BY T. P. Matthews (402) 536-4733 TELEPil0NE May, 1985 MONmi DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Neti 484.8 485.1 37 i
483.8
_ 484.7 ig 2
484.1 3
19 482.6 481.2 484.0 20 4
483.9 480.8 5
21 483.4 480.1 6
22 482 9 23 7
482.4 479 I s
24 401*0 478.0 25 9
476.3 10 480.8 26 479.6 475.5 11 27 479*2 476.3 12 28 480.0 13 29 482.3 14 30 475.6 475.9 15 31 484.5 16 INSTRUCTIONS On this format.!ht the average daily unit power Icvelin MWe-Net for each day in the reporting inonth. Compute io the nearest whole megawatt.
(9/77) 8506240037 850 b5' PDR ADOCK O g
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,:e OPERATING DATA REPORT DOCKET NO.
50-285 DATE June 7.1985 COMPLETED BY T. P. Matthews TELEPHONE (402) 536-4733 OPERATING STATUS Notes Fort Calhoun Station
- 1. Unit Name:
. 2. Reporting Period:
May, 1985 1500
- 3. Licensed Thermal Power IMWt):
502
- 4. Nameplate Rating (Gross MWe):
470
- 5. Design Electrical Rating (Net MWe):
502
- 6. Masimum Dependable Capacity (Gross ilWe):
478
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Lesel To which Restricted.lf Any (Net MWe):
N/A None
- 10. Reasons For Restrictions,if Any:
This Month Yr.-to Date Cumulatise 744.'0
-3,623.0 102,409.0
- 11. Hours in Reporting Period 744.0 3,596.6 78,876.8
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Rewne Shutdown flours 0.0 0.0 1.309.6
- 14. Hours Generator On-Line 744.0-3,588.7 78,256.1 0.0 0.0 0.0
- 15. Unit Resene Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 1,111,352.9
_5_,299,096.5 99,485,863.5
- 17. Gross Electrical Energy Generated (MWH) 375,038.0 _,
1,801,024.0 32,570,649.0 357.81T.7 1,719.094.3 31,130,731.6
- 18. Net Electrical Energy Generated (MWH) 100.0-99.1
-76.4
- 19. Unit Senice Factor
- 20. Unit Availability Factor 100.0 99.1 76.4 100.6
-99.3 66.1
- 21. Unit Capacity Factor (Using MDC Net) 100.6 99.3 63.9
- 22. Unit Capacity Factor (Using DER Net) -
- 23. Unit Forced Outage Rate 0.0 0.0 3.6
- 24. Shutdowns Scheduled Over Nest 6 Months IType.Date.and Duration of Each t:
1985 Refuelina Shutdown is tentatively scheduled for October.1985 with start up in December, 1985.
25.. If Shut Down At End Of Report Period. Estimated I are of Startup:
N/A 26.' Units in Test Status IPrior to Commercial Operationp N/A.
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICIIY COMMERCIAL OPER ATION N/77)
s 50-285 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE June 7. 1985 COMPLETED BY T-P Matthowt May,1985 TELEPHONE (402) 536-4733 REPORT MON DI e,
E E
.5 E 3
j.$ 3 Licensee
, r, ja, Cause & Corrective E
Action to No.
Date g
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Event p
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y 5
jgg Report a mV Prevent Recurrence H
g d
There were no unit shutdowns during the month of May,1985.
s
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l 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions
' S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 84faintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination 5
. F Administrative Exhibit I - Same Source G-Operational Error (Explain)
(9/77)
Il-Other (Explain)
S
~
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Refueling Information Ebrt Calhoun - Unit No.1 Beport for the nonth ending May,1985 1.
Scheduled date for next refueling shutdown.
October. 1985 2.
Scheduled date for restart following refueling.
December. 1985 3.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes If answer is yes, what, in general, will a.
these be?
Technical Specifications change to accomodate
-increased radial peaks due to further reduction in radial leakage.
b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review CtxTtittee 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 action and support infonration. ~
Seotember. 1985 5.
Inportant licensing considerations ~ associated with refueling, e.g., nea or different fuel design or supplier, unreviewed design ~or performance analysis nothods, significant changes in fuel design, nea operating procedures.
Methodology Changes June, 1985 6.
'Ihe number of fuel assemblies: a) in the core-133 assemblies b) in the spent fuel pool 305 c) spent fuel pool storage capacity 720 d) planned spent fuel pool May be increased storage capacity via fun 1 nin
~ consolidation 7.
The projected date of the last refueling that can be discharged to the spent fuel pool' assuming the present licensed capacity.
1oog June 3, 1985 Prepared by M,
Date y
r.
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 May, 1985 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at 100% power throughout the month of May, 1985.
Requalification and hot license simulator training at Combustion Engineering in Windsor, Connecticut, continued through May. Hot license training _for two engineers and four operators continued-through May.
The Maintenance and Technical departments continued preparation for the refueling outage scheduled this fall.
The Chemical and Radiation Protection group prepared high level shipments and normal shipments during May. The Auxiliary Building-cleanup of stored waste will greatly improve background exposures in this area.
Security improvements continued to be implemented per schedule.
No safety valve or PORY challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS None B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.
_ CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL 4
Procedure.
Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since-it only' involved.the evaluation of data from a surveillance test to verify that a fuel assembly
' uplift condition did not exi.st.
h'.
m m
1 m
Monthly Operations Report May, 1985 Page Two D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)
Procedure Description SP-SOV-1 Periodic Cycling of Solenoid Valves Preventive Maintenance to Maintain 79-91B Qualification.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 as it merely assured that solenoid valves which corre-spondtospecificsafetyrelatedvalveshavebe$n cycled to ensure they remain qualified per the District's Electrical Equipment Qualification Program.
System Acceptance Committee Package for May,1985:
Package Description / Analysis EEAR FC-84-62 Repair Damaged Stud Hole RL-2A Primary Manway.
This modification restored the primary m6nway stud hole to its original integrity following Combustion Engineering's reconnended repair procedure. This modification has no adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS During the month of May, the biannual leak rate surveillance test for the containment purge valves was completed.
The total leakage for Penetrations M-87 and M-88 was 2,800 sccm.
This is actually 2,322.2 sccm lower than the previous six-month test, which now decreases the Type B and C total from 11,749.73 sccm to 9,427.53 sccm.
The new B and C leak rate of 9,427.53 sccm is well below the allowed leakage of.6 La (62,951 sccm) as specified in 10CFR50 Appendix J.
The nex't scheduled test that will affect the B and C leak rate totals is the biannual PAL door surveillance test.
F.
CHANGES IN PLANT OPERATING STAFF None
4 Monthly Operations Report May, 1985 Page Three G.
TRAINING During May, three auxiliary operator (nuclear) candidates successfully completed qualification boards. Training for the six hot license can-didates continued.
Sir.olator requalification training of licensed operators continued. Annual emergency preparedness refresher training commenced.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Package Description Amendment No. 88 This amendment revises the Technical Specifications to add requirements related to the reactor protec-tion system and the engineered safety features actu-ation system that would limit the length of time that a channel in these systems may be bypassed.
If the length of time is exceeded, then the channel must be tripped.
Amendment No. 89 This amendment adds new Technical Specifications which will require OPPD to implement and maintain a program to ensure the capability to obtain and analyze a reactor coolant sample and containment atmosphere sample under accident conditions.
II. MAINTENANCE (Significant Safety Related)
None
. E%
y, W. Gary Gates Manager Fort Calhoun Station I
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'As Omaha Public Power District 1623 Harney Omaha. Nebtaska 68102 402/536 4000 t
June 13, 1985 LIC-85-255 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Conmission j
Washington, DC 20555
Reference:
Docket No. 50-285
Dear Mr. Taylor:
flay Monthly Operating Report Please find enclosed ten (10) copies of the May,1985 Monthly Operating Report for the Fort Calhoun Station Unit No.1.
Sinc rely,
?!'?_ l R. L. Andrews Division Manager p
Nuclear Production RLA/TPit/dao 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 INP0 Records Center American Nuclear Insurers NRC File g
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'g 45 W4 EmpMymen h ua Oppoqundy
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