ML20080C874
| ML20080C874 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/10/1982 |
| From: | William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20080C870 | List: |
| References | |
| LIC-82-403, NUDOCS 8308290354 | |
| Download: ML20080C874 (10) | |
Text
h AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.
WIT Fort Calhoun Station DATE December 10, 1982 COMPLETED BY T. P. Matthews (402)536-4733 TELEPilONE MONm November, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 301.8 376.3 i
,7 2
303.4 376.1 ig 3
306.0 376.3 39 4
305.4 376.0
,o 304.8 374.7 s
7, 306.3 374.9 6
2, 7
306.7 374.8 23 g
306.5 375.7 24 9
308.5 378.4 25 307.8 378.5 in 26 ii 316.9 378.6 27 12 344.0 379.5 28 13 369.0 379.5 29 i4 374.9 378.9 39 15 375.9 3,
16 376.5 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) 8308290354 830824 PDR ADOCK 05000285 p
OPERATING DATA REPORT DOCKET NO.
50-285 DATE December 10, 1982 COMPLETED BY T. P. Matthews TELEPHONE (4021536-4733 j
OPERATING STATUS Fort Calhoun Station Notes
- 1. Unit s.ime:
November, l'Jd2
- 2. Reporting Period:
l
- 3. Licensed Thermas Power (MWt):
1500 601
- 4. Nameplate Rating (Gross MWe):
Design Electrical Rating (Net MWe):
501
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Masimum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
None I
- 9. Power Level To Which Restricted. If Any (Net MWe):
N/A None
- 10. Reasons For Restrictions.If Any:
l 1
This Month Yr..to.Date Cumulative
)
I
- 11. Hours in Reporting Period 720.0 8,016.0 80,497.0
- 12. Number Of Hours Reactor Was Critical 720.0 7,801.5 64,040 3
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5
- 14. Ilours Generator On.Line 720.0 7,787.5 62,8//.5
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 788.152.6 10,832,932.7 77,534,762.8
- 17. Gross Electrical Energy Generated (MWH) 767,6 34 J_ _ _.
3.633.373.9 25.707.319.5
- 18. Net Electrical Energy Generated (MWH) 251.817.1 3,455,732.6 24,303,601.1
- 19. Unit Sersice Factor 100.0 97.1 78.1
- 20. Unit Availshility Factor 100.0 97.1 78.1
- 21. Unit Capacity Factor (Using MDC Net) 73.2 90.2 65.6
- 22. Unit Capacity Factor (Using DER Net) 73.2 90.2 65.3
- 23. Unit Forced Outage Rate 0.0 2.9 3.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of F hl:
1983 refueling outage comenced December 7, N82, earlier than planned, due to a forced outage resulting from turbine bearin9 and rotor blade problems.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
March 15, 1983
- 26. Omt,in Test Status (Prior to Commercial Operation,. N/A Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIAL OPER A TION (9/77)
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L
est 50-285 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME IMTE _ December 10. 1982 COMPLETED 11Y T. P. Matthews REPORT MONTig November, 1982 TELEPilONE (402)536-4733
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Y Licensee E t, fe, Cause & Corrective 4,s jg5 Event 37 g'y No.
Date g
3g Action to 5 ;ji e Repori a vi V Prevent Recurrence H
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6 There were no unit shutdowns during the month of November, 1982.
4 l
l l
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l I
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equiprnent Failure (Explain) 1 Manual foi Preparation of Data B Maintenance of Test 2-Manual Scrarn.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Repor (LER) File (NUREG-D Regulatory Restriction 4 Other (Explain) 0161)
E. Ope ator Training & license Examination F-Administ ratise 5
i G-Operational Error (Explain)
Exhibit I-Same Sourec (9/77)
Il-Other (Explain) l
Refueling Information Ebrt Calhoun - Unit No.1 Peport for the mnth ending November 1982 1.
Scheduled date for next refueling shutdown.
March, 1984 2.
Scheduled date for restart following refueling, tiay, 1984 3.
Will refueling or resumption of operation thereafter regaire a technical specification change or other license amendment?
Yes a.
If ansm r 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 Paview Ccanittee 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?
4.
Scheduled date(s) for submitting proposed licensing action and support information.
February, 1984 5.
Irportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfornmco analysis nethods, significant changes in fuel design, new operating procedures.
6.
2e number of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728 7.
We projected date of the last refueling that can be discharged to the spent fuel pool assuning the present licensed capacity.
1985 Prepared by
/7/>ydl Date December 1. 1982 o
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g.
OMIC4A'PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 November,1982 -
1 Monthly Operations Report I.
OPERATIONS SU'&aRY Fort Calhoun Station began increasing power November 11, 1982 from 65% power while Hebraska City vent off line. The plant was stabilized
)
at 785 power November 13, 1982 and: remained at that power level through i
the rest or the month.
t Four bundles of new fuel were received, November 3,1982.
Annual' licensed operator requalification examinations are under way 3
and will be completed December 2, 1982.
No safety valve or PORV challenges occurred.
A.
PERFOBTICE CHAPACTERISTICS I
LER Number Deficiency NONE 4
B.
CHANGES IN OPEPATING METHODS
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NONE
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t C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONE I
S aveillance tests as required by the Technical Specifications-Section 3.0 and Appendix B, were performed in accordance with
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the annual surveillance, test schedule. The following is a su= mary of the surveillance tests which resulted in Operation Incidents and are not reported elsewhere in the report:
Operation Incidents Deficiency OI-1597 ST-SUTEMP-1 During performance of Surveillance Test, TIA-135 and TIA-136 indicators ~ vere erroneously logged.
t OI-1601 ST-ESF-6 DGk,governorboosterpumpmotorwasremoved and sent.out for repair.vithout maintenance s
' order.
OI-1602 ST-DG-2, During perforicance > of ST-DG-2, _ several switches
)
i F.1, F.2, noticed to?be out of calibration-tolerance.
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F.3 J
Speed Sensing Svitch, jacket water pressure,
. lube, oil high-temperature alarm, fuel' oil base j
tank level.
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ifont'hly Op.eratiohs Report November,.1982 Page Two
. C.-
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS (Continued)
', 3,,
Operation Incidents Deficiency
,f 0I-1506 ST-CSA-1, While performing test, it was dis-
'F.6-covered that Group 4 PPDIL & PDIL
+-'
setpoints set a higher value than y
they were supposed to.
D.'
CHANGES < TESTS.AND EXPERIMENTS CARRIED OUT WITHOUT COM-MISSION APPROVAL Procedure' Description
/
ST-FE-1 Visual inspection of spent fuel.
Completed per procedure.
This procedure did not constitute
'j' an unreviewed safety question per 10CFR50.59 since any potential
- 'I ' }
accidents have been evaluated in the FSAR section on " Final Handling Accidents".
f
, -SP-SFS-1 Shipment of Spent Fuel in NL1-1/2 Completed per procedure.
Cask.
u This procedure did not constitute N~-
an unreviewed safety question per 10CFR50.59 since redundant rig-y ging was used and a potential fuel handling accident has been analyzed in the FSAR.
SP-UF -1 23 Uranium Hexafluoride Storage Cylin-6 9-27-82
~ der External Visual Inspection.
9-29-82 Completed per procedure.
10-1-82 10-5-82 Performance of this procedure did not constitute an unreviewed safety question as defined by 10CFR50.59.
Handling and storage of the UF6 is in accordance with license SMC-1420 and thus does not affect the station operating l
license.
The safety impact of UF6 release would be less severe than that of other types of chemical releases which have 7
already been evaluated.
a Pavised 8/24/83 9
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Monthly Operati6ns Report November,.1982 Page Three D.
CHANGES, TESTS AND EkPERTMENTS CARRIED OUT WITHOUT COM-
6 9-17-82 Completed per procedure.
9-29-82 10-1-82 Performance of this procedure did 10-5-82 not constitute an unreviewed safety question ~as defined by 10CFR50.59.
Handling and storage of the UF6 is in accordance with license SMC-1420 and thus does not affect the station operating license.
The safety impact of UF6 release would be less severe than that of other types of chemical releases which have already been evaluated.
SP-NFR-1 Fuel Receipt :/rocedure.
Completed per procedure.
Performance of SP-NPR-1 did not constitute an unreviewed safety question per 10CFR50.59.
New fuel receipts were performed in-strict accordance with the station operating license and applicable' regulations.
No possibility existed of a signi-ficant radiological release in the event of"bishandling.
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 evaluating data from a surveillance test.
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Revised 8/24/83
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Monthly Operations Report November, 1982 Page ?our E.
RESULTS OF LEAK RATE TESTS
- 0
- IE F.
CHA:IGES I:i PLAIIT OPERATIIG STAFF NONE G.
TRAI:iING Training for November,1982:
Operators, NRC licensed personnel were administered an annual requalification exam.
Non-licensed operators were trained on systems, theory and procedures. on an as needed basis.
All operators received lectures on Emergency Procedures, the newly installed H2 analyzer SER, and reactor theory.
All plant personnel attended general employee training refresher en a scheduled basis in preparation for the 1983 outage.
Maintenance received training on systems as scheduled.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRIliG NUCLEAR REOULATORY CO:0!ISSION AUTHORIZATIGIT PURSUANT TO 10CFR50 59 NONE l
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1 Monthly Operations Report a
November, 1982 i
P, age Five II.
MAI:iTE'IANCE (Significant Safety Related) 1 M. O.
Date Descri7 tion Corrective Action 16875 10-11-82 RM0/60 pump vill not start breaker Removed motor and replaced.
tripped free.
16S77 10-20-82 Charging Pu=p, CH-1A packing cooling Completed per MP-CH-1-1, tank overfills when pump is shutdown.
i 16913 10-25-82 HCV-2633 valve has no indication valve replaced.
light.
16839 10-20-82 B/PIC-905 Sigma failed to reset.
Removed, repaired and reinstall-ed sigma.
16797 10-28-82 Replace motor & brake on CRDM-17 Replaced rectifier.
16937 10-29-82 NI "A" vide range channel irratic Re-calibrated.
indication.
16936 10-29-82 UI "D" vide range channel B-10 Re-calibrated.
detector irratic indication.
16921 10-28-82 S/G Pressure sigma low pressure trip Replaced indicsting light, j
light blinks.
16961 10-28-82 ROD #23 vill not operate.
Repaired NC contract in raise relay.
17203 11-5-82 TIA-221 sig=a appears to have failed.
Replaced alarm circuit.
16990 11-22-82 RM-055A needs to be cleaned.
Cleaned RM-055 16935 10-28-82 RC-23 Steam Generator leak on hand-Machined gacket surface and hole.
repaired.
16933 10-28-82 RC-2A Steam Generator south handhole Machined gasket surface and leaks.
repaired.
l 16934 10-27-82 RC-2A Steam Generator handhole leaks.
Machined gasket surface and repaired.
16798 10-27-82 RC-23 support rod broken.
Repair per procedure.
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W. G. Gates i
Plant Manager
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3s23 maRNtv e O M a H A. NEGRAEMA 69102 a TEL EPHON E S38 4000 ARE A CODE 402 December 13, 1982 LIC-82-403 1
Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement l
U. S. Nuclear Regulatory Comission Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. DeYoung:
Please find enclosed ten (10) copies of the November Monthly Operating Report for the Fort Calhoun Station Unit No.1.
Sincerely, W. C. f)%
y ones Division Manager Production Operations WCJ/TLP:jem Enclosures cc: NRC Regional Office Office of Management &; Program Analysis (2)
Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Mr. L. A. Yandell - NRC Senior Resident Inspector Nuclear Safety Analysis Center NRC File M -
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