ML20003E928
| ML20003E928 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/10/1981 |
| From: | Tira Patterson OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20003E922 | List: |
| References | |
| NUDOCS 8104170505 | |
| Download: ML20003E928 (9) | |
Text
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^vta^ct ori'v usiT eowta ttvt' DOCKET NO. *50-285
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UNIT Fort Calhoun #1 DATE April 10, 1981 COMPLETED BY T. L. Patterson TELEPHONE (402)S36-4413 March, 1981 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 304.9 17 305.9 2
306.2 is 307.5 3
306.8 39 307.2 305.9 4
20 307.2 306.0 5
21 306.0 6
305.1 305.8 22 7.,
305.4 23 305.2 8
306.8 305.6 24 307.1 25 305.2 9
10 308.9 26 305.0 307.2 304.7 11 27 307.3 304.1 12 28 305.5 13 29 303.8 14 307.0 30 304.7 306.1 304.4 15 3
305.2 16 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
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(9/77) 810417o505
OPERATING DATA REPORT DOCKETNO. 50-285 DATE April 10, 1981 CONIPLETED BY
~. L. Patterson TELEPHONE L402)536-4413 OPERATING STATUS
- 1. Unit Name:
Fort Calhoun Station Unit No.1 Notes
- 2. Reporting Period:
March, 1981
- 3. Licensed Thermal Power (51Wt):
1500
- 4. Nameplate Rating (Gross 51We):
501
- 5. Design Electrical Rating (Net 51We): 478
- 6. Sla[imum Dependable L pacity (Gross 51We):
501 478
- 7. Maximum Dependable Capacity (Net SIWE):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
Electrical ratings changed to reflect plant capacity tests run durii a February. This was the first full capacity run since stretch power.
- 9. Power Lesel To Which Restricted,1f Any (Net SIWE): N/A
- 10. Reasons For Restrictions.If Any:
N/A a
This Stonth Yr.-to.Date Cumulative
- 11. Ilours in Reporting Period 744.0 2.160.0 65.881.0
- 12. Number Of flours Reactor Was Critical 744.0 2,127.1 51,905.4
- 13. Reactor Reserve Shutdown flours 0.0 0.0 1,30915
- 14. Ilours Generator On-Line 744.0 2.106.3 50.366.2
- 15. Unit Resene Shutdown liours 0.0 n.n 0.0
- 16. Gross Thermal Energy Generated (51Wil) 727,396.2 2,343,941.5 62,062,181.8
- 17. Grow Electrical Energy Generated (51Wil) 243,310.0 783,818.0 20.572.089.6
- 18. Net Electrical Energy Generated (51Wil) 227,612.8 737,404.1 19,435,587.0
- 19. Unit Senice Factor 100.0 97.5 77.2
- 20. Unit Availability Factor 100.0 97.5 77.2
- 21. Unit Capacity Factor (Using 51DC Net) 64.0 70.3 64.7
- 22. Unit Capacity Factor (Using DER Net) 64.0 70.3 64.3
- 23. Unit Forced Outage Rate 0.0 2.5 4.0
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
Refueling, September 15. 1981. 7 Weeks
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INIIIA L CRITICALITY INITI AL ELECTRICITY CO\\l%1ERCIA L OPER ATION (9/77)
50-285 UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. --Fort Calhoun #1 UNIT N AME DATE April 10, 1981 REPORT MONTil March, 1981 COMPLETED BY T. L. Patterson
(
TELEPilONE (4021536-4413 n.
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Licensee Eg e.
Cause & Corrective No.
DJte i
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js.5 Event F. ?
o-3 Action to
~5:
Report *
(E U Prevent Recurrence y5 5
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No shutdowns this month.
1 I
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 14f anual for Preparation of Data 1141aintenance 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 & License Examination F Administrative 5
G Operational Error (Explain)
Exhibit 1 - Same Source (9/77) li-Oiher (Explain )
Refueling Information Fort Calhoun - Unit No. 1 Report for the nonth ending March 1981 1.
Scheduled date for next refueling shutdown.
September 15, 1981 2.
Scheduled date for restart following refueling.
November 15, 1981 3.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No a.
If anner is yes, what, in general, will these be?
b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Coninittee to deter-mine whether any unreviewed safety questions are associated with the core reload.
No c.
If no such review has taken place, when is it scheduled?
September 1, 1981 4.
Scheduled date(s) for submitting proposed licensing action and support infor ration.
5.
Inportant 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.
l 6.
The number of fuel assemblies: a) in the core 133 asserrblies l
b) in the spent fuel pool 197 l
c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483 7.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1985 Date April 10, 1981 Prepared by g../.
f OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 March 1981 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun was operated at approxinately 65% power for the month of March.
The training shifts for each week are participating in requalification training at the Co=bustion Engineering simulator facility in Windsor, Connecticut.
The Supervisor-Operations attended a three-day workshop at Combustion Engineering facilities in Windsor, Connecticut, to rewrite Energency Procedures. This rewrite, when compiled, will be submitted to the NRC around June 1, 1981.
Surveillance tests and operational tests were completed as scheduled.
Preparations for the fall refueling outage have been initiated.
There were no PORV or safety valve challenges.
A.
PERFORMANCE CHARACTERISTICS None B.
CHRTGES IN OPERATING METHODS None C
RESULTS OF SURVEILLANCE TESTS AIID INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a summary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:
Operations Incident Deficiency 01-1103 ST-DG-2, Level, Pressure, and Temperature Instru-F.1 & F.5 ment Calibration, DG-2.
Several instru-ments were recalibrated satisfactorily.
Diesel operability was not affected.
01-1105 ST-ERM-1 Unable to collect milk samples at the Wolfe Dairy Farn.
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Monthly Operations Report March 1981 Page Two D.
CHANGES, TESTS AND EXPERIME'ITS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descrintion/ Safety Analysis Summary SP-FAUD-1 Fuel Assembly Uplift Condition Detection the two operable Ap channels shows greater than 99%
assurance that the 150 pound criterion is not being violated.
SP-FAUD-1 Fuel Assembly Uplift Condition Detection the two operable Ao channels shows greater than 99%
assurance that the 150 pound criterion is not being violated.
An unreviewed safety question as defined in 10CFR50 59 did not exist as this procedure only involves evaluating data from a surveillance test.
MR-FC-81-2h Replacement of Mechanical Snubbers /renoved the mechanical snubber with a hydraulic snubber on SIE-20h.
This did not constitute an unreviewed safety question as defined in 10CFR50.59 since the replacement snubber met or exceeded the design criteria and all limitations of the Technical Specifications were followed for the replacement.
FC-79-2h Moisture Separator Drain Lines - Completed as designed.
This procedure did not constitute an unreviewed safety question as defined in 10CFR50.59 since this work was on a non-safety related system.
EEAR No. 78-63 Reactor Coolant Pump RC-3C Seal Water Pipe Vibration /ccepleted as designed.
This modification did not constitute an unre-viewed safety question as defined by 10CFR50.59 since it did effect the pressure retaining l
boundary of the RCS or the operability of the RC pumps. The modification was made to reduce vibration of cooling piping to the RC pump.
SP-FE-5 Spent Fuel Inspection Stand Installation and/or Removal.
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f Monthly Operations Report 4
March 1981 Page Three i
D.
CHANGES, TESTS A*TD EXPERIME'iTS CARRIED OUT WITHOUT C0!CIISSION APPROVAL-Procedure Descriotion/ Safety Analysis Summary SP-FE-5 (Continued)
Procedure performed to remove the fuel inspection stand from the spent fuel pool in preparation for Refueling 1981. Appropriate crane controls were used to prevent the possibility of moving loads over ' spent fuel. No Tech. Specs. or system opera-bility effects are involved so an unreviewed i
safety question is not in question.
DCR FC-78-5 Rerouting of piping around MOV-CV turbine control valve seat drain.
This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 since the work was done on a non-safety related system.
i E.
RESULTS OF LEAK RATE TESTS No Leak Rate Tests during the month of March.
F.
CHANGES IN PLANT OPERATING STAFF i
None G.
TRAINING l
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Training for the month of March included simulator training for licensed operators. The annual requalification exam was given to some licent,ed operators. A review of the current training manual was completed in preparation for updating. Maintenance departments continued to receive systems and technical training i
as scheduled. General employee training (badge training) was held on Monday and Friday of each week. Records are being computerized for all training held at the Fort Calhoun Station.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COIO!ISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. 57 which deletes interim Technical Specifications on Handling of Spent Fuel Cack.
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MA M;4A3C3 (Significant Safety Related) 1
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- Date Description Corrective A::icn i
7298 2-18-81 "B" subcooled margin monitor not Put in new solid state chips.
operating properly.
Retested.
9057 2-18-81 CH-1A sight glass broken.
Installed new flow tube.
8712 2-19-81 "D" Channel TU-3 intermittingly Recalibrated.
j pre-tripping.
9050 2-17-81 FCV-1101 cannot be closed from the Replace piston "O" ring in Control Room.
Indication shows operator.
closed but valve is half-open.
9127 2-23-81 Performed mechanical tests on Completed. All snubbers mechanical snubbers 51, 52, 53, satisfactory.
5h, 55 and 10h05.
89h6 2-19-81 Replace fire pumpemegraded battery.
Completed.
9206 2-27-81 CH-1B packing cooling pump leak.
Replaced motor and pump.
9053 2-17-81 RPS "B" vide range not providing full Recalibrated.
7 DPM in cal. position.
922k 2-27-81 DG-2 Secondary Air start regulator Rebuilt regulstor.
leaking.
1 7770 1-16-81 CH-179 leaks.
Completed per MP-RV-1.
8888 2-5-81 RM-060 would hot trip VIAS in test-Changed fail light pushbutton.
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9216 2-27-81 Diesel Gen. #2 Tachometer vill not Replaced Tach.
I meet CP-SPECS.
9211 3-2-81 RPS Channel A AT power calibrate Replaced.
pot. causing flucuation of power greater than 10% power during i
channel adjustment.
9575 3-13-81 DG-1 Diesel Air Compressor engine Adjusted valves and tuned up.
running rough.
9233 3-1-81 CH-lC Charging Pump pumping less Replaced suction and discharged than other charging pumps.
valves and repacked pump.
Returned to service.
95h3 3-10-81 DG-2 Diesel Air Compressor will not Adjusted valves and returned to istart.
service.
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Mcnthly Operaticns Reper
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Descricticn Ocrrective Acticn hh35 2-13-80 DG-2 Repair electrical cable Replaced connector and tested entrance into governor.
operability.
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9553 3-11-81 CH-1A charging pump oil leak from Tightened fitting.
j oil pressure switch.
9170 2-26-81 CH-1B charging pump packing leak.
Repacked and replaced gaskets.
9535 3-11-81 HCV h02B position indication Cleaned and adjusted.
malfunction.
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