ML20128C264
| ML20128C264 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/1985 |
| From: | Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20128C258 | List: |
| References | |
| NUDOCS 8505280233 | |
| Download: ML20128C264 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.
UNIT Fort Calhoun Station May 6, 1985 DATE T. P. Matthews COMPLETED BY (402) 536-4733 TELEPHONE April, 1985 MONTH-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Neti 484.8 484.2 I
17 483.5-2 482.9 is 482.4 484.8 19 3
482.5 484.6 20 4
484.5 481.2 5
2:
484.4 480.0 6
22 485.2 480.5 7
23 483.3 485.0 24 8
485.1 485.3 9
25 486.1 485.1 26 to 485.2 486.8.
II 27 487.0 12 28 484.5 486.7 13 29 484.8 485.9
.g4 30 485.4 ls 3,
484.9 16 INSTRUCTIONS On this format. list the average daily unit power Icvel in MWe Net for caph day in the reporting inonth.Cmnpute to the nearest whole rnegawatt.
(9/77) 8505280233 850515 DR ADOCK 05000285 PDR i
(_
OPERATING DATA REPORT DOCKET NO.
50-285 DATE May 6, 1985 COMPLETED BY T. P. Matthews TELEPHONE (402) 636-4733 OPERATING STATUS Fort Calhoun Station Notes
- 1. Unit Name:
- 2. Reporting Period:
April, 1985 1500
- 3. Licensed Thermal Power (MWt):
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
- 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 719.0 2,879.0 101.665.0
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 719.0 2,852.6 78,132.8 0.0 0.0 1,309.5
- 13. Reactor Reserve Shutdown Hours 719.0 2,844.7 77.512.'1
- 14. Hours Generator On.Line 0.0 0.0 0.0
- 15. Unit Reserve Shutdown flours
- 16. Cross Thermal Energy Generated (MWil) 1.072.284.2 4.187.743.6
_ 48.374.8i10.6
- 17. Gross Electrical Energy Generated (MWH) 364,792.0 _,
1,425,986.0 32.195.611.0 348,26F.9 1,361,277.1 30,772,914.4
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor 100.0 98.8 76.2 100.0 98.8 76.2
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net) 101.3 98.9 65.8 101.3 98.9 63.6
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 0.0 0.0 3.7
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:
1985 Refuelina Shutdown is tentatively scheduled for October 1985 with startup in December, 1985.
- 25. If Shut Down At End of Report Period. Estimated Date of Startup:
N/A
- 26. Units in Test Status (Prior to Commercial Operation):
N/A Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)
L.
i 50-285 DOCKET NO.
Fort Calhoun Station UNIT SHUTDOWNS AND POWER REDUCHONS UNIT NAME DATE May 6,:,985 COMPLETED BY
,. P. Matthews-402) 536-4733 April,1985 TELEPHONE i
REPORT MONTH "L
t h
Cause & Corrective E
.5 ?
}
Y Licensee 3g g
,g g 5 Event 5?
c3 Action to Nu
!U Prevent Recurrence No.
Date c.
5 35g Report
- u e
Q There were no unit shutdowns during the month of April, 1985.
-o 4
3 i
1 2
Exhibit G -Instructions Method:
1-Manual for Preparation of Data F: Forced Reason:
S: Scheduled A-Equipment Failure (Explain) 2-Manual Scram.
Entry Sheets for Licensee 3-Automatic Scram.
Event Report (LER) File (NUREG-B-Maintenance of Test C-Refueling 4-Other (Explain) 0161)
D-Regulatory Restriction E-Operator Training & License Examination 5
F-Administrative Exhibit I - Same Source G-Operational Eirur (Explain) 01/77)
Il-Other (Explain)
'N*
-empee'ep $3 g t_
~.5
n-Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending April. 1985
.l.
Scheduled date for next refueling shutdown.
Oc tnhar. 1 QAR 2.
Scheduled date for restart following refueling.
December. 1QRR 3.
Will refueling or resunption of operation thereafter require a technical specification change or other license amendment?
yc 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 ansser is no, has the reload fuel design
'and core configuration been reviewed by your Plant Safety Review Ccumittee 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.
Jentamhar, 199 :
5.
Inportant licensing considerations associated with refueling, e'.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes'in fuel design, new operating procedures.
Methodology Changes June, 1985 6.
The number of fuel assemblies: a) in the core 13, assemblies b) in the spent fuel pool anc; c) spent fuel pool storage capacity 790 d) planned spent fuel pool May be increased storage capacity via ryal jpo 7.
The projected date of the last refueling that can be discharged.to the spent fuel pool assuming the present licensed capacity.
igge:
Prepared by h GM Date.
Ma.v 1. 14ng
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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 April, 1985 Monthly Opyrations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at a nominal 100% power throughout April, 1985.
The Technical group continued to conduct a program to identify vacuum leaks on the Fort Calhoun condenser.
This program was successful, indicating the primary source of leakage was the dogbone seal which has been coated to reduce condenser inleakage.
Two new auxiliary operators-nuclear were hired in April. Annual NRC licensed operator-requalification simulator training at Combustion Engineering in Windsor, Connecticut, began in April.
-Hot license training for two enginears and four operators is in progress.
The first A0N training group using lesson plans are permanently on shift.
Training of the initial A0N class and the current hot license class continued on schedule. Accreditation efforts continue with emphasis on the C/RP training area.
The NRC conducted a security audit during April which resulted-in the potential close out of many long standing areas of concern.
No safety valve or PORV challenges or failures occurred.
A.
PERFORMANCE CHARACTERISTICS LER Number Description 85-001 VIAS Actuation (RM-060).85-002 VIASActuation(RM-061).85-003 RM-061 VIAS Actuations.
B.
CHANGES IN OPERATING METHODS None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None L
(, < ;; ai
~~ '
c.
JMonthly Operations Report f
- April' 1985 a
Page Two' D.E JCHANGES, TESTS?AND EXPERIMENTS CARRIED OUT.WITHOUT COMMISSION APPROVAL'
. Procedure Description SP-FAUD-1
. Fuel Assembly Uplift Condition Detection.
This procedure did not constitute an unreviewed' safety question as defired by 10CFR50.59 since-
.it only. involved the evaluation of data from a surveillance' test te verify that a fuel assembly.
uplift condition did not exist.
SP-LI0H Lithium Hydroxiue Moisture Carryover Test.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the concentration of the lithium in the steam l generators was lower than the concentration limit of sodium which is more damaging to the
. secondary system than_ lithium.
System Acceptance Committee Package for April, 1985:
Package Description / Analysis EEAR FC-84-116-HCV-1930 Replacement.
This modification replaced the screenwash strainer backwash valve,~HCV-1930.
The Jamesbury 2" ball valve was' replaced by a 2" Red Valve' cylinder-actuated " pinch" valve. This modification did not effect safety related equipment; therefore,--
has no adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS None F.
CHANGES IN PLANT OPERATING STAFF During April, Mr. Matt Anielak and Mr. Doug Foreman reported to the Fort Calhoun Station as Auxiliary Ope ~rators-Nuclear. Mr. Timothy J. McIvor replaced Mr. Alan W. Richard as Supervisor-Technical.
El
F:
. j,d -
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Monthly Operations Report April, 1985 Page Three e
G.
TRAINING During April, C/RP, Maintenance,- Auxiliary Operator and Hot License training continued.
Three requalification groups attended simulator training at Combustion Engineering.
INP0 made a two-day training assistance visit.
Operator job and task analysis continued.
H.
. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION-AUTHORIZATION PURSUANT T0 10CFR50.59 Package Description Amendment No. 86 This amendment revises the Technical Specifications to incorporate the requirements of Appendix *I of 10 CFR Part 50 as the Radiological Effluent Techni-cal Specifications (RETS).
Amendment No. 87 This amendment adds new Technical Specifications addressing the operability and surveillance require-ments for the new Toxic Gas Monitoring System. The amendment also makes an administrative change such that there are not two tables in the Technical Specifications numbered 2-9.
II. MAINTENANCE (Significant Safety Related)
None W. & N W. Gary Gates Manager Fort Calhoun Station L'