ML20101E777
| ML20101E777 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/06/1984 |
| From: | Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20101E775 | List: |
| References | |
| NUDOCS 8412260397 | |
| Download: ML20101E777 (10) | |
Text
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i AVERAGE DAILY UNIT POWER LEVEL L
DOCKET NO.
50-285 UNIT Fort Calhoun Station December 6, 1984 DATE ews COMPLETED BY (402) 536-4733 TELEPHONE MONTH November, 1984 D \\Y AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 484.9
.484.3 g
g7 294.7 485.2 gg 2
485.7 0,0 3
39 485.1 0.0 4
20 0.0 484.3 21 5
0'0 400*7 6
22 484.9 0.0 7
23 484.9 0.0 8
24 0.0 485.4 25 9
10 484,8 26 0.0 484.9 0.J 11 27 400'0 0.0 12 28 484.4 0.0 13 29 484.4 0.0 14 30 484.0 15 483.8 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe. Net for each day in the reporting month. Compute o the nearest whole megawatt.
19/771 O h hB5 PDR L
OPERATLNG DATA REPORT DOCKET NO.
50-285 6, 1984 DATE s-COMPLETED BY T. P. Matthews TELEPHONE (402) 536-4733 OPERATING STATUS Notes Fort Calhoun Station
- 1. Unit Name:
November, 1984
- 2. Reporting Period:
1500
- 3. Licensed Thermal Power (MWt):
501
- 4. Nameplate Rating (Gross MWe):
478
- 5. Design Electrical Rating (Net MWe):
501
- 6. Maximum Dependable Capacity (Gross MWe):
478
- 7. Maximum Dependable Capacity (Ner MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
N/A
- 9. Power Level To which Restricted if Any (Net MWe):
N/A None
- 10. Reasons For Restrictions,if Any:
This Month Yr. to Date Cumulative 720.0 8.040.0 98.042.0
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 427.5 4,670.6 74.564.5 0.0 0.0 1,309.5
- 13. Reactor Reserve Shutdown !!ours
- 14. Hours Generato On-Line 426.9 4,563.4 73,965.9'
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 629,244.7 6,482.772.6 93,242,486.3
- 17. Gross Electrical Energy Generated (MWill 214,626 0_,,,
2.134.892.0 30.452.461.0 3
- 18. Net Electrical Energy Generated (MWH) 204,844.0 2,030,658.4 29.110.527.1
- 19. Unit Senice Factor 59.3 56.7 75.4 59.3 56.7 75.4
- 20. Unit Availability Factor 59.5 52.8 64.7
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Cap.icity Factor (Using DER Net) 59.5 52.8 62.4 40.7 6.4 3.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Each):
None.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
N/A
- 26. Units in Test Status tPrior to Commercial Operation):
N/A Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION (9/77)
L
r 50-285 DOCKET NO.
Fort Calhoun Station UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME DATE _Decamhar 6. E84 T.
P. Matthews COMPLETED BY November-1984 TELEPHONE (402) 536-4733 REPORT MONTH w.
E E
Cause & Corrective E_ g 3
$ E5 Licensee
,E t, je.,
Action to N...
Date t
3g s
js5 Event 37 g?
U Prevent Recurrence mV y:
jgg Report a g
r 6
84-04 841118 F
293.1 A
1 N/A CB VALVEX Unit was taken off-line at 1852 hrs to repair leaking' pressurizer spray valve PCV-103-1. While the unit was down for repair of the valve, other routine maintenance was performed.
4 3
Exhibit G -Instructions I
2 Method:
for Preparation of Data F: Furad Reason:
l-Manual S: Scheduled A-Equipment Failure (Explain) 2-Manual Scram.
Entry Sheets for Licensee Event Report (LER) File (NUREG-Bataintenance of Test 3-Automatic Scram.
C Refueling 4-Other (Explain) 0161)
D-Regulatory Restriction L4)perator Training & License Examination 5
Exhibit i. Same Source F-Adnunistratise G4)perational Error (Explain)
Il-Other (Esplain)
(T77)
Refueling Information Ebrt Calhoun - Unit No.1 Report for the nonth ending November 1984 October 1985 1.
Scheduled date for next refueling shutdown.
December 1985 2.
Scheduled date for restart following refueling.
3.
Will refueling or restmption of operation thereafter require a technical specification change or other Y"8 license amendment?
a.
If answer is yes, what, in general, will those be?
Technical Specification change to accommodate increased radial peaks due to further redution in radial leakage.
b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safoty Review Ctanittee to deter-mine whether any unroviewed safety questions are associated with the core roload, c.
If no such review has taken place, when is it scheduled?
4.
Scheduled dato(s) for submitting proposed licensing action and support information.
September 1985 5.
Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unroviewed design or performance analysis incthods, significant changes in fuel design, new Methodology dianges June 1985 operating procedures.
6.
no number of fuel assemblies: a) in the coro 133 assemblics b) in the spent fuel pool 30 5 c) spent fuol pool storago capacity 729 d) planned spent fuel pool May be increased storago capacity vin fuel nin consolidation 7.
@o projected dato of the last refueling that can be discharged to the spent fuci pool asstming the present licensed capacity.
1996 Prepared by_
Q/h)ld tuto December 3, 1984 g
e
}
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 November, 1984 Monthly Operations Report I.
OPERATIONS SUMARY Fort Calhoun Station operated at 100% power until November 18,1984, when the unit was shut down to repair a leaking pressurizer spray valve. Plant heatup was in progress on November 30, 1984.
Two operators received their NRC Reactor Operator License. One Reactor j-Operator resigned during November, 1984.
No safety valve or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-010 VIAS Actuation (RM-051).84-020 Containment Hydrogen Analyzer Impairment.
B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-VA-80 Hydrogen Purge System Test.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this proce-dure only checks operability of fans and cleanliness of the filters.
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 exist.
(
Monthly Operations R: port November,1984 Page Two D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL t
(continued)
Procedure Description SP-UF6-1 Uranium Hexaflouride Storage Cylinder External Visual Inspection.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it simply. -
consisted of inspection and verifying the integrity of UF6 storage containers.
i SP-CHEM-4 Spiked Radiological Samples for Laboratory Analysis Comparison.
7 This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it provided offsite laboratory analysis for which shipment is pre-scribed in Title 10 and Title 49 of the Code of Federal Regulations.
System Acceptance Committee Packages for November, 1984:
Package Description / Analysis EEAR FC-82-25 Air Filter System for Fort Calhoun Maintenance Shop.
This modification provided for the safe assembly of the welding ventilation system in the mainten-ance shop. This modification has no adverse effect on the safety analysis.
EEAR FC-82-87 Storage Rack for Refueling Tools.
This modification provided for the fabrication and installation of a storage rack to hang from the spent fuel pool walkway over the waste drum storage area to provide adequate space for storage of refueling tools. This modification has no adverse effect on the safety analysis.
EEAR FC-84-47 Catalyst Bed Assembly Replacement for VA-81A and VA-818.
This modification provided for the replacement of catalyst bed assemblies for VA-81A and -VA-818 to increase their reliability.
This modification has no adverse effect on the safety analysis.
L
. Monthly: Operations.RIport November,1984 Page Three D.
CHANGES, TESTS-AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued).
System Acceptance Comittee Packages for November,1984: '(continued)
Package Description / Analysis EEAR FC-84-123 AC-338 Union Installation.
This modification provided for the installation of a union upstream of CH-lC oil cooler CCW inlet relief valve.AC-338 to allow easier removal and
' installation of AC-338 during maintenance. This modification has no adverse effect on the safety analysis.
EEAR FC-84-154 "D" Channel RC Flow Transmitter D/dPT-ll4X Changeout.
This modification provided for the replacement of a Barton model transmitter with a Rosemount model. This modification has no' adverse effect on the safety analysis.
EEAR FC-84-24 Containment Sump Post Accident Level Hi-Lo Alarm.
This modification deleted Lo level alarm since more reliable instrumentation has been installed.
This level has two other annunciator windows besides the level indicators.
This modification has no adverse effect on.the safety analysis.
EEAR FC-84-32 Concentrate Boric Acid Tank CH-llA and CH-llB Hi Temperature Alarm.
This modification raised the setpoint on the hi temperature alarm for the boric acid tanks.to eliminate a nuisance alarm on the control boards.
This setpoint is below the system design tempera-ture in the USAR.
This modification has no adverse effect on the safety analysis.
EEAR FC-84-34 100# Hydrogen Header Pressure Hi-Lo Alarm.
This modification deleted the low pressure alarm for the 100# hydrogen header to eliminate a nuisance e
alarm on the control boards.
This header is only pressurized for short periods to charge volume control tanks and during these periods, pressure indication is closely watched by operations. The-hi alarm will be retained.
This modification has no adverse effect on the safety analysis.
L'
o 1
e I
_ Monthly Operations R; port November, 1984 Page Four D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)-
System Acceptance Committee Packages for November,1984:
(continued)
Package Description / Analysis EEAR FC-84-35 Radwaste Solidification System Trouble.
This modification deleted the ATCOR radwaste system trouble alarm since the system has not been declared operational.
This modification has no adverse effect on the safety analysis.
EEAR FC-84-36 Gas Stripper Malfunction Alant This modification deleted the nuisance alarm on this system which is not in service.
This modification has no adverse effect on the safety analysis.
EEAR FC-84-38 200# Nitrogen Header Pressure Hi-Lo Alarm.
This modification increased the 200# nitrogen header relief valve NG-123 setting and the high alarm setpoint for this nitrogen header.
This modification has no adverse effect on the safety analysis.
EEAR FC-84-44 Waste Disposal System and Waste Evaporator Malfunction Alarm.
This modification rewired alarm initiation off of the local alarm horn relay only to provide an alarm in the control room until the alarm is locally acknowledged. This will also pro-vide an alarm in the control room Jonora l=-=-
ringback. This modification,har=no adverse effectonthesafgtyanElysis.
E.
RESULTS OF LEAK RATE TESTS During the month of November, local type C leak rate tests were performed on penetrations M48, M87 and M88. With the exception of penetration M88, leak rates were found to be in tolerance.
Original as found leak rate associated with penetration M88 was found to be 7.8 scfm.
Following repairs per Maintenance Order No. 843572, final (as left) leakage was measured to be 22.2 sccm.
\\
L
L Monthly Operations R: port November, 1984 Page Five E.
RESULTS OF LEAK RATE TESTS (continued)
The overall effect of the leak rates performed in November was to
-increase the total (a's left) type B and C leak rate from 7,684.33 sccm, which was the combined (as left) type B and C leak rates measured at the end of the 1984 refueling outage, to 10,039.83 sccm.
The difference of 2,355.5 sccm is mainly attributable to the increased leakage associated with penetration M87.
F.
CHANGES IN PLANT OPERATING STAFF Mr. William vonForell resigned as Reactor Operator (SR0) in November, 1984.
G.
TRAINING During November,1984, two hot license candidates successfully completed an NRC administered Reactor Operator examination and have obtained licenses. The NRC also administered written and walk through oral examinations for seven licensed operators and staff as part of a new exam criteria recently enforced. All seven successfully completed the oral portion. The results of the written portion will not be available for approximately six weeks. Requalification training continued as scheduled including systems, controls and theory training.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)
M.0.#
Description 843289 PCV-103-1 Repair 843567 PCV-103-2 Replace trim 843551 HCV-6738 Replace valve 843651 HCV-1041C Replace bonnet gasket 845227 HCV-1041A Repack 845228 HCV-1041B Repack e
- Monthly Operaticns Report s
~
- November,1984 Page,Six.
II. MAINTENANCE (Significant Safety Related) (continued) vi, M.0.#
Description
/.
845225 FT-319 Leaks 845226
-FT-332 Leaks 842067
.HC't-176 Dual indication
-g 842632 CEOM #41 Roa sticks 843453 HCV-1385 Check contactors i
843454 HCV-1386 Check contactors p.
s W. Gary Gates Manager Fort Calhoun Station d
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