ML20239A309
| ML20239A309 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1987 |
| From: | Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| LIC-87-619, NUDOCS 8709170256 | |
| Download: ML20239A309 (9) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL i
DOCKE'1 NO.
50-285 UNIT Fort Calhoun Station!
DATE September 6, 1987 COMPLETED BY T. P. Matthews TELEPil0NE 402-536-4733 August, 1987 MONTil DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(Mwe. Net) 1 467.0 473.6
,7 466.7 2
18 475.2 467.3 479.4 3
,9 467.5' 4
20 481.8 5
470.5 481.6 21 474.6 401'1 6
22 7
475.0 480.8 1
23 476.4 j
8
-24 482.5 9
474 9 25 484.1 474.6 484.0 10 26 11 27 486.2 12 474.1 485.6 28 476.1 484.8 13 475.9 483.5 14 39 15 475.7 483.0 3,
4 4*
16 i
INSTRUCTIONS l
On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to l
the nearest whole megawatt.
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OPERATING DATA REPORT t
50-285 i
DOCKET NO.
DATE Santernhor 8,1C87 COMPLETED BY T. P. flatthews 1
TELEPHONE 402-536-4733 I
OPERATING STATUS l
l Fort Calhoun Station Notes
- 1. Unit Name:
- 2. Reporting Period:
August, 1987 l
1E00
- 3. Licensed Thermal Power (MWt):
502
- 4. Nameptaie Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
47R 502
- 6. Maximum Dependable Capacity (Gross MWe):
i
- 7. Maximum Dependable Capacith (Net MWe):
(
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
1 l
N/A 1
- 9. Power Level To Which Restricted,1f Any (Net MWe):
- 10. Reasons For Restrictions. lf Any:
l l
This Month Yr..to Date Cumulative
- 11. Hours in Reporting Period 744.0 5,831.0 122,137.0
- 12. Number Of flours Reactor Was Critical 744.0 3,579.3 93,91U.0
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5
- 14. Hours Generator On Line 744.0 3,602.7 92,989.8
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1.110,094.9 5,121,161.8 120,171,663.7
- 17. Gross Electrical Energy Generated (MWH) 372,046.0 _
1,711,347.0 39,478,073.2
- 18. Net Electrical Energy Generated (MWH) 354.998.6 1,631,599.8 37,715.060.7 l
- 19. Unit Service Factor 100.0 61.8 76.T 1
- 20. Unit Availability Factor 100.0 61.8 76.1
- 21. Unit Capacity Factor (Using MDC Net) 99.8
- 58. 5__ _
66./
- 22. Unit Capacity Factor (Using DER Net) 99.8 58.5 64.8
- 23. Unit Forced Outage Rite 0.0 0.0 3.2
)
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date.and Duration of Each):
)
None i
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITI A L CRITICALITY INITIA L ELECTRICITY N/A CO)1 MERCI A L OPER ATION j
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Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending July 1987 1.
Scheduled date for next refueling shutdown.
Seotember 1988 2.
Scheduled date for restart following refueling.
December 1988 3.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes a.
If answer is yes, what, in general, will these be?
Possible transition to 24 month cycles.
b.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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 propot,ed licensing action and support information.
Auaust 1988 5.
Important 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.
6.
The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 393 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel nin consolidation 7.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1996 Prepared by M N Date September 3. 1987
j l
1 OMAHA PUBLIC POWER DISTRICT l
Fort Calhoun Station Unit No-.1 l
August, 1987 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station operated at 100% power through August, 1987.
Walkdown of all fire barriers in the Station and needed repairs were J
completed.
Progress continued on the Station modification reduction 1
program and the welding program. Work continues on the new training facility and warehouse. The NRC performed an inspection of the program for testing of check valves.
A two week INP0 MART (Maintenance Assistance and Review Team) self-assessment inspection was performed.
One operator was hired during August, i
No safety valves or PORV challenges or failures occurred.
l A.
PERFORMANCE CHARACTERISTICS None B.
CHANGES IN OPERATING METHODS l
None C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None
{
i D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-PRCPT-1 Post Refueling Core Physics Testing and Power Ascension.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the Cycle 11 low power physics testing was completed with acceptable results.
All predictions were within the acceptance criteria for the measured values.
Power ascension was accomplished in a safe manner in accordance with fuel preconditioning guidelines.
~
t tionthly Operations Report.
August, 1987 Page Two D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)
Procedure Description SP-SAMP-1 Procedure to Verify HCV-2503 Closed.
This proceduce did not const'tute an unreviewed safety question as defined by 10CFR50.59 because j
while verifying that HCV 2503 is in the closed position, the related containment isolation valves, HCV-2504A/B, remained operable during the test.
SP-FW-10 Inspection of Feedwater Flow Nozzles, FW-1102/1398 I
and FW-1101/1395.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50 59 since an i
inspection was performed on the feedwater flow nozzles only, measuring orifice and pipe diameters.
No maintenance or change to existing 1
. systems occurred. The test found the nozzles to l
be in excellent condition with no significant change in dimensions occurring.
System Acceptance Committee Packages for August, 1987:
Packa_ge Description / Analysis I
EEAR FC-82-024 Firearms Range.
l This modification provided for sealing the construction of a firearms range at the Fort Calhoun Station.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-83-005 Storage of Equipment in Containment.
This modification provided for the construction of a storage platform located in containment.
This modification does not have an adverse effect on the safety analysis.
i
1 Manthly Operations Report August, 1987 Page Three D.
CHANGES, TESTf, AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued) i System Acceptance Committee Packages for August, 1987:
(continued) i PacKaue Description / Analysis EEAR FC-84-188 Pressuriur Spray Valve Replacement.
q This modification provided for replacement of f
pressurizer spray valves PCV-103-1 and PCV-103-2 and asscciated adjacent piping, and for the 3
addition of new seal leakoff temperature switches t
TS-198-1 and TS-198-2.
Pipe supports were I
modified based on new reactor coolant piping loads l
and movements.
This modification does not have an e
adverse effect on the safety analysis.
j EEAR FC-85-100 Radioactive Gas Decay Tank Pressure Transmitter Upgrnde.
This modification provided for the recalibration of four existing pressure transmitters to an expanded range.
The existing panel mounted indicators were replaced in kind with an expanded scale.
This modification was in response to Reg.
Guide 1.97 Rev. 2.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-86-064 Diesel Generator Turbocharger Replacement.
1 I
This modification provided for increased reliability of the diesel generator turbocharger due to modifications made by CMD in the new turbocharger oil system.
These modifications are requested by EMD for standby power generators that require emergency fast starts.
This modification does not have an adverse effect on the safety analysis.
1 EEAR FC-87-015 HVAC Security Barriers.
I I
This modification provided for improvements to the site security system.
This modification does not have an adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS None i
Monthly Operations Report August, 1987 Page Four F.
CHANGES IN PLANT OPERATING STAFF During August, 1987, fir. Mike Anderson was hired as a Helper.
G.
TRAINING Di: ring August, Station Training continued technical staff and managerial personnel training.
Licensed operator requalification rad-equipment operator-nuclear auxiliary building training continued during the month.
H.
CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment N o.,_
Description 110 This amendment revises the Technical Specifications by adding the Inadequate Core Cooling Instrumentation which is required by It6m II.F.2 of NUREG-0737, " Clarification of TMI Action Plan Requirements", November 1980.
This amendment is effective October 30, 1987, which is 60 days from date of issuance (August 31, 1987).
II.
MAINTENANCE (Significant Safety Related)
None.
/M ' /
7 ),]&
W. Gary Gat 4s Manager-Fort Calhoun Station
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.6 Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 September 14, 1987 LIC-87-619 j
U. S. Nuclear Regulatory Commission Document Control Desk i
Washington, DC 20555 I
Reference:
Docket No. 50-235 l
Gentlemen:
)
SUBJECT:
August Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),
please find enclosed, one copy of the August 1987 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.
Sincerely,
/k W
R. L. Andrews Division Manager Nuclear Production RLA/me Enclosures c:
NRC Regional Office Office of Management & Program Ar.alysis (2)
R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File (FCS)
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