ML20205P376
| ML20205P376 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/1986 |
| From: | Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| LIC-86-217, NUDOCS 8605210386 | |
| Download: ML20205P376 (10) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.
UNIT Fnrt Palhn9n Station DATE May 5, 1986 T. P. Matthews COMPLETED BY TELEPHONE 402-536-4733 MONTH April. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 329.5 17 481.0 481.2 473.6 is 2
480.4 480.7 i,
3 480.3 4
20 479 9 5
481 3 21 479.6 479 7 481.0 22 6
480.9 479.8 7
23 480.5 8
24 479.1 478.9 9
ann 1 25 478.7 to 480.0 6
479 7 II 27 476.6 478.9 477.8 12 28 479.0 478.2 13 29 479.8 30 478.3 i
14 480.7 15 3,
481.1 16 l
INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
(9/77) 8605210386 860430 DR ADOCK 05000285 PDR
_ tea 9 Yi
OPERATING DATA REPORT DOCKET NO. 50-285 DATE May 5, 1986 COMPLETED BY T. P. Matthews TELEPitONE 407-M6-4733 OPERATING STATUS Notes
- 1. Unit Name: Fort Calhoun-Station
- 2. Reporting Period: Apri1. 1986
- 3. Licensed Thermal Power (MWt):
1500 502
- 4. Nameplate Rating (Gross MWe):
478
- 5. Design Electrical Rating (Net MWe):
502
- 6. Maximum Dependable Capacity (Gross MWe):
470
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report.Give Reasons:
N/A N/A
- 9. Power Lesel To Which Restricted.If Any (Net MWe):
- 10. Reasons For Restrictions. If Any:
None This Month Yr..to-Date Cumulative 719.0 2,879.0 110,425.0
- 11. Ilours In Reporting Period 719.0 2,683.6 84,429.0
- 12. Number Of flours Reactor Was Critical
- 13. Reactor Reserve Shutdown flours 0.0 0.0 1.309.5
- 14. liours Generator On-Line 719.0 2.507.7 83.630.6 0.0 0.0
'0.0
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWil) 1.062.459.6 3.018.497.8 106.769.542.4
- 17. Gross Electrical Energy Generated (MWH) 357,192.0 1,002,441.2 34,987,010.2 341,198.9 955,006.2 33,432,899.6
- 18. Net Electrical Energy Generated (MWil) 100.0 87.1 75.7
- 19. Unit Service Factor 100.0 87.1 75.7
- 20. Unit Availability Factor 99.3 69.4 65.6
- 21. Unit Capacity Factor IUsing MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 99.3 69.4 63,6 0.0 0.0 3.T
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Eacht:
None N/A
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status IPrior to Commercial Operation):
Forecast Achiesed INIIIAL CRITICALITY INITI AL ELECTRICITY N/A COMMERCI A L OPER ATION (9/77)
DOCKETNO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS tort Calhoun 5tation UNIT NAME DATE May 5, 1986 COMPLETED BY T. P. flatthews REPORT MONHf Act'll 1986 TELEPHONE 402 8i36-4733 w
O C
5,, E "h
- Y3 Licensee
,En,,
{*'8 Cause & Corrective No.
Date g
3g 2se Event g?
Action to gO f:
5 j gji g Report a mO Prevent Recurrence W
g 6
There were no unit shutdowns or power reductions during the month of April, 1986.
j 1
2 3
4 s
F: Forced Reason:
Method:
Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Renriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explaif)
Exhibit 1 Same Source (T77)
Il-Other (Explain) i i
Refueling Information Ebrt Calhoun - Unit No. 1 l
Report for the nonth ending Aoril.1986 1.
Scheduled date for next refueling shutdown.
March, 1987 i
2.
Scheduled date for restart following refueling.
May, 1987 4
3.
Will refueling or resunption of operation thereafter require a technical specification change or other license amendment?
Yes j
a.
If answer is yes, what, in general, will these be?
l Fuel supplier change from ENC to CE and possible Technical Specification change.
b.
If answer is no, has the reload fuel design and core configuration been reviewed by I
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?
i 4.
Scheduled date(s) for submitting proposed licensing action and support infocrtion.
February, 1987 5.
Inportant licensing oansiderations associated with refmling, e.g., new or different fuel design or supplier, unreviewed design or perforriance analysis methods, significant changes in fuel design, new i
operating procedures.
I New fuel supplier (Combustion Engineering) but the new fuel will be essentially the i
i same as that supplied by Combustion
]
Engineering for Cycle 5.
i 6.
The number of fuel assenbliest a) in the core 133 assemblies b) in the spent fuel pool 348 4
c) spent fuel pool storage capacity 729 d) planned spent fuci pool May be increased t'
storage capacity via fuel nin consolidation 7.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
t oors i
Prepared by Date May 1, 1986
'*'M*M***?~****~ ***M~~'"~~~%~~~"*'*~**~~
~ ~ ~ -
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 April, 1986 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station reached 100% power on April 3,
- 1986, following a brief power reduction to 30% due to out of specification secondary chemistry parameters.
The plant remained at 100% power for the rest of the month.
During the month, all uranium hexafluoride (UF ) stored on 6
site was shipped to Martin Marietta, Inc., in Paducah, Kentucky.
Annual simulator training for NRC licensed plant staff began in April at the Combustion Engineering simulator in Windsor, Connecticut.
Five groups spent time at the simulator during April.
During April, an Auxiliary Operator-Nuclear initial training class was completed.
Equipment Operator-Nuclear (Auxiliary Building) classroom training was also completed.
Accelerated requal training for one RO and one SRO who failed the March NRC requal exam was conducted.
Non-licensed operator refresher training and general employee training continued.
No safety valve or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS None B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Nono
Monthly Operations Report April, 1986 Page Two l
D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.
l This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a surveil-lance test to verify that a fuel assembly uplift condition did not exist.
SP-CTPC-1 Core Thermal Power Calculation (NSSS Calorimetric).
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provides for recording of plant data and performing calculations.
No equipment is affected.
SP-UF6-1 Uranium Hexafluoride Storage Cylinders External Visual Inspection.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provided for an inspection of a storage area and associated items, and loading of filled UF6 containers prior to shipping.
Operability of plant equipment was not affected.
i SP-UF6-2 Loading and Off-Loading of UF6 Cylinders.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 as an accidental release of toxic gas during UF6 cylinder loading is addressed by the actions of AOP-28 and is evaluated in the USAR in Section 14.23.
L
i s
Monthly Operations Report April, 1986 Page Three l
l D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued) 1 g escription j
Procedure D
j i
SP-UF6-3 Evacuation of Uranium Hexafluoride Cylinders.
This procedure did not constitute an unreviewed safety question as defined i
by 10CFR50.59 as an accidental release of toxic gas during UF6 cylinder shipment preparations is addressed by 4
the actions of AOP-28 and is evaluated
{
in the USAR in Section 14.23.
j SP-BURNUP-1 Burnup Determination for Storage of j
Spent Fuel.
]
This procedure did not constitute an i
unreviewed safety question as defined by 10CFR50.59 because the procedure only provides for calculating the burnup and acceptance for storage of spent fuel bundles in accordance with Technical Specifications.
No equipment operability is affected.
SP-PRCPT-1 Post Refueling Core Physics Testing and Power Ascension.
This procedure did not constitute an unreviewed safety question as defined j
by 10CFR50.59 because the procedure provided for low power physics testing j
and power ascension in accordance with Technical Specifications.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it involved the pressurization of the vent header with water for the purpose of detecting l
leakage in the system.
This procedure i
did not involve any equipment that is j
part of any USAR accident safety analyses.
The margin of safety as defined in the basis for Tech. Spec.
j 2.9.1.B (Gaseous Effluents) was not reduced by performing this procedure.
l I
Y
Monthly Operations Report April, 1986 Page Four D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)
System Acceptance Committee Packages for April, 1986:
Packace Description / Analysis EEAR FC-80-93 Safety Injection Solenoid Valves.
This modification provided for the replacement of existing solenoid valves with safety qualified CQE solenoid valves.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-81-14 Mechanical Operators for Feedwater Suction / Discharge Valves.
This modification provided for the installation of converto gear manual drives on nine valves in the feedwater system.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-84-49 Installation of Additional Memory into the ERF Computer System.
This modification provided for the installation of two new disk drives and additional memory in the TSC ERF computer.
This modification does not have an adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS None F.
CHANGES IN PLANT OPERATING STAFF None i
Monthly Operations Report April, 1986 Page Five G.
TRAINING During April, an Auxiliary Operator-Nuclear initial training class was completed.
Equipment Operator-Nuclear (Auxiliary Building) classroom training was also completed.
Accelerated requal training for one RO and one SRO who failed the March NRC requal exam was conducted.
Non-licensed operator refresher training and general employee training continued.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Anendment No.
Description 96 The amendment updates the snubber table listings to reflect the removal and addition of snubbers.
The amendment also changes the surveillance require-ments for the nuclear detector well cooling annulus exit air temperature detectors to make them consistent with the associated limited condition for operation.
II.
MAINTENANCE (Significant Safety Related)
None
- w. & 2 ~=
W. Gary Gates Manager Fort Calhoun Station i
)
s Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402!536-4000 May 15, 1986 LIC-86-217 n
Mr. James M. Taylor, Director Office of Inspect *on and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Reference:
Docket No. 50-285
Dear Mr. Taylor:
April Monthly Operating Report Please find enclosed ten (10) copies of the April,1986 Monthly Operating Report for the Fort Calhoun Station Unit No.1.
Sincerely, GS feu R. L. Andrews Division Manager Nuclear Production RLA/TPM/me Enclosures cc: NRC Regional Office Office of Management & Program f.nalysis (2)
Mr. R. R. Mills - Combustion Er.gineering Mr. R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers l
NRC File l
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