ML20107C241
| ML20107C241 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/31/1985 |
| From: | Mathews T OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20107C232 | List: |
| References | |
| NUDOCS 8502210232 | |
| Download: ML20107C241 (8) | |
Text
.
OPERATING DATA REPORT 50-285 DOCKET NO.
DATE Februarv 6, 1985 CONIPLETED BY T. P. Matthews TELEPilONE (402) 536-4733 OPERATING STATUS Notes Fort Calhoun Station
- 1. Unit Name:
- 2. Reporting Period: January, 1985 1500
- 3. Licensed Thermal Power (31Wt):
501
- 4. Nameplate Rating (Gross alWe):
478
- 5. Design Electrical Rating (Net SIWE):
501
- 6. hlaximum Dependable Capacity (Gross htWe):
470
- 7. Slaximum Dependable Capacity (Net alwe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
N/A N/A
- 9. Power Level To which Restricted.lf Any (Net SlWe):
None
- 10. Reasons For Restrictions. If Any:
This Stonth Yr.-to-Date Cumulative 744.0 744.0 99,530.0 i1. Ilours in Reporting Period 744.0 744.0 76.024.2
- 12. Number Of Ilours Reactor Was Critical 0.0 0.0 1.309.5
- 13. Reactor Reserve Shutdown llours 744.0 744.0 75.411.4'
- 14. Ilours Generator On-Line 0.0
_0 J._.
0.0
- 15. Ur.it Reserve Shutdown llours 1,108.294.9 95.295.061.9 1,108,294.9
- 16. Gross Thermal Energy Generated (SIWil)
- 17. Gross Electrical Energy Generated (SIWil) 377 3L4 0....
377.374.0 11.146.000.n 2
1 360,547.8 360,547.8 29,772,185.1
- 18. Net Electrical Energy Generated (51Wil) 100.0 100.0 75.8
- 19. Unit Service Factor 100.0 100.0 75.8
- 20. Unit Availability Factor 101.4 101.4 65.1
- 21. Unit Capacity Factor (Using SIDC Net) 101.4 101.4 62.9
' 22. Unit Capacity Factor (Using DER Net) 0.0 0.0 3.8
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Slonths (Type. Date.and Duration of Each):
None N/A
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation): N/A Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CONINlERCI AL OPERATION 8502210232 850213 PDR ADOCK 05000285 (9/77)
R PDRg
50-285 DOCKET NO.
Fort Calhoun Station
' UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT N AME February 6. 1985 DATE COMPLETED 8Y
.. P. Matthews 402) 536-4733 January, 1985:
TELEPHONE t
REPORT MONTH t
.5 ?
"h Y
Licensee 5%
f4 Cause & Corrective
~
No.
Date g
gg s
.g g 5 Event 7
n3 Action to EU f'
Prevent Recurrence
$5 5
j g5 g Report
- 6 There were no unit shutdowns or power reductions during the month of
~
January,,1985.
t I
4 3
Exhibit G - Inst ructions i
2 Method:
for Preparation of Data F: Forced Reason:
1-Manual S: Scheduled A Equipment Failure (Explain) 2-Manual Scram.
Entry Sheets for 1.ieensee Event Report (LER) File (NUREG-IbMaintenance of Test 3 Automatic Scram.
016I)
C Refueling 4 Other (Explain)
D-Regulatory Restriction E-Operator Training & License Examination 5
F-Administrative Exhibit 1 - Same Source G Operational Error (Explain)
(9/77) llother(Explain)
1 Refueling Information Ebrt Calhoun - Unit No.1 Report for the nonth ending January, 1985 1.
Scheduled date for next refueling shutdown.
October 1985 2.
Scheduled date for restart following refueling.
December 1985 3.
Will refueling or resunption of operation thereafter require a technical specification change or other license amendment?
Yes a.
If answer is yes, what, in general, will these be?
Technical Specification change to accommodate increased radial peaks due to further reduction in radial leakage, b.
If answer is no, has the reload fuel design and core configuration been revicwed by 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?
4.
Scheduled date(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, unreviewed design or perfomanm analysis nuthods, significant changes in fuel design, new operating procedures.
liethodology Changes June 1985 6.
The number of fuel assenblies: a) in the core 133 assmblies b) in the spent fuel pool 305 c) spent fuel pool storage capacity 729 d) planned spent fuel poolllay be increased storage capacity via fuel pin consolidation 7.
'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present 1996 licensed capacity.
Prepared by_
M Date February 4,1985 r
e y
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-285 Fort Calhoun Station us 7 February 6, 1985 DATE T. P. Matthews COMPLETED BY (402) 536-4733 TELEPHONE MONTH January. 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe Net) 485.6 482.0 i7 i
485.2 482.6 I8 2
484.6 482.9 39 3
484.8 483.7 20 4
486.2 484.2 5
483.3
'486.2 22 6
484.6 484.7 23 7
484.4 483.7 24 8
483.7 483.7 25 484.3~
10 -
484.0 26 483.2 484.7 27 484.4 484.1 12 23 486.9 13 29 486.1 485.4 34 39 486.4 486.1 33 3,
486.6 16 INSTRUCTIONS On this format. list the average daily unit power levelin MWe-Net for each day in the reporting anonth. Compute to the nearest whole megawatt.
Wl77)
. m
y
- s OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 January, 1985 Monthly Operations Report I.
0PERATIONS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power throughout January, 1985. A Reactor Operator was promoted to Shift Supervisor effective January 16, 1985. A Shift Supervisor transferred to the Training Department.
No. safety valve or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-008 Steam Generator Tube Rupture.84-014 VIAS Actuation (RM-060).84-015 Load Over the RCS.84-024 VIAS Actuation (RM-061).84-023 VIAS Actuations (RM-060, RM-050)84-025 RM-060 VIAS Actuation.
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-BURNUP-1 Burnup Determination for Storage of Spent Fuel.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it verifies that burnup criteria are met for spent fuel storage as required in the NRC approved spent fuel rack installation.
L
a Mo'nthly Operations R: port
' January, ' 1985
-Page Two
[
D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)
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 exist.
SP-EEQ-1 LOCA Qualified Electrical Equipment Identification Check.
This procedure did not constitute an unrevi.1wed safety question as defined by 10CFR50.59 because this proce-dure is simply an inventory list of qualified equipment and indications located on various panels and control boards in the plant.
No plant operations or evolutions are involved.
SP-SI-4 Loop Valve Setting Procedure.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because' it was per-formed in accordance with an approved procedure and accomplished the desired results.
SP-50V-1 Periodic Cycling of Solenoid Valves Preventive Maintenance to Maintain 79-01B. Qualification.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this proce-dure aids in assuring all valves needed to attain hot shutdown following an accident are operable.
This is accomplished through' periodic cycling via the qualified life program.
System Acceptance Committee Packages for January, 1985:
Package Description / Analysis EEAR FC-83-33 TSC Room Modification.
This modification provided for the installation of a sliding glass door between Room 107 and Room 115 in the TSC and has no adverse effect on the safety analysis.
m.
1-Monthly Op; rations R port January, 1985 Page Three D.
CHANGES, TEST AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)
System Acceptance Committee Packages for January,1985:
(continued)
Package Description / Analysis EEAR FC-83-68 Installation of LCV-1196 and 1197 Valves.
This modification did not effect safety related eqeipment, therefore, has no adverse effect on the safety analysis.
EEAR FC-83-82 Auxiliary Building Communication.
This modification did not effect safety related equipment, theretcre, has no adverse effect on the safety analysis.
EEAR FC-84-53 Automatic Rod Withdrawal Alarm.
This modification provided for the deletion of this alarm. This alarm is considered a nuisance alarm since the rods are never controlled in the automatic mode and are never planned to be. Also, the three conditions that give this alarm are individually annunciated on three separate windows.
This modification has no adverse effect on the safety analysis.
EEAR FC-84-151 Diesel No. 1 Solenoid Valve Replacement.
This modification provided for a one-to-one replacement of solenoid valves and rotated control levers on associated air motors. This will provide for correct operation of the intake dampers.
This modification has no adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS Procedure ST-CONT-2, Section F.2, was completed on January 23, 1985.
This is the six month Personnel Air Lock Leak Rate Test. The new as found leak rate increased the total Type B and C Local Leak Rate from 10,139.73 sccm to 11,749.73 sccm.
This is well within the.6 La specified in Appendix J. 10CFR50.
F,,o,
Monthly Op; rations Report i
January, 1985 Page Four F.
CHANGES IN PLANT OPERATING STAFF l
Mr. James B. Michael was promoted to Shift Supervisor effective January 16, 1985. Mr. George J. Pelnar transferred from the Operations Department as Shift Supervisor to the Training Department.
I G.
TRAINING Operators received extensive fire brigade leader training in addition to preplanned lecture series. A Self Evaluation Report (SER) was submitted to the Institute of Nuclear Power Operation (INP0) for the operator non-licensed, initial licensed and licensed requalification programs. This is three of ten programs that will be certified a.nd accredited by INP0.
Training was conducted for Quality Control personnel on non-destructive testing. Training was also conducted in the areas of General Employee Training (Initial and Requalification), systems and emergency plan for plant personnel.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)
None
- w. & k W. Gary Gates Manager Fort Calhoun Station L_
_ -.