ML20154G078
| ML20154G078 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/31/1988 |
| From: | Blessie W, Gates W, Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| LIC-88-718, NUDOCS 8809200237 | |
| Download: ML20154G078 (10) | |
Text
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7 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE Seotember 9. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 MONTH Auaust 1988 OAl AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,
(MWe-Net) (MWe-Net) 1 408 17 365 2 406 18 362 3 407 19 364 6 4 410 '40 365 5 414 21 367 6 416 22 368 7 416 23 369 8 416 24 369 9 418 25 368 10 _.
418 26 370 11 419 27 372 12 418 28 374 13 415 29 375 14 411 30 375 15 406 31 374 16 377 ,
INSTRUCTIONS On this format, list tLe average daily unit power level in MWe-Net for each day ,
in the reporting month. Compute to the nearest whole megawatt.
8809200237 ggog33 f
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l OPERATING DATA REPORT :
t DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE Sootenbor 9. 1988 l COMPLETED BY W. J. B' ess' e !
TELEPHONE 402-536-459S OPERATING STATUS
- 1. Unit Name Fort Calhoun S<:at<on Notes i
- 2. Reporting Period: Auaunt 3 80 '
- 3. LicensedThermalPower(Wtp : 1500 ;
- 4. NameplateRating(GrossMWeJ: 502
- 5. Design Electrical Rating (Net We): 478
- 6. Maximum Dependable Capacity (Gross MWe): 502
- 7. Maximum Dependable Capacity (Net MWe): 478
- 8. IfchangesoccurinCapacityRatings(ItemsNumber3Through7)SinceLastReport, Give Reasons:
N/A l
- 9. Power Level to Which Restricted, If Any (Net We): N/A
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744.0 5855.0 130.921.0
- 12. Number of Hours Reactor Was Critical 744.0 5855.0 102.694.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 :. 309.5
- 14. Hours Generator On-l.ine 744.0~ 5855.0 10L.773 L
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (WH) 951.709.3 092.8 132.408.7;.s.0
- 17. Gross Electrical Energy Generated (WH) 307.298.0 . . 322.0 43.592.263.2
- 18. NetElectricalEnergyGenerated(MWH) 290.624.0 2.408.373.8 41.632.356.6
- 19. Unit Service facto.' .,00.0 ,00.0 77.7
- 20. Unit Availability Factor :.00.0 :.00.0 77.7 21 Factor (Usin MOC Net? 8'..? 88.9 69.0
- 22. Unit Capacit Factor (UsingDERhet) 81.7 88.9 67.1-
- 23. Unit Forced tage Rate 0.0 0.0 2.9
- 24. ShutdownsScheduledOverNext6 Months (Type Date, and Duration of Each):
,,,,,_ The 1988 Refuel'na Shutdorn if tentativelyscheduledforSeptember 24. 1988 w' th startuo tentat< volv schec ulecI for December 10. 1988.
- 25. If Shut Down at End oo Report Per1od, Estimated Oate of Startup: N/A
- 26. Units In Test ' .tus (Prior to Commercial Operation): Forcast Achieved
'NITIAL CRITICALITY
.lTIAL ELECTRICITY N/A
.JmERCIAL OPERATION
DOCKET NO. 50-285 UNIT SHUIDOWNS AND POWER REDUC' DONS UNIT NAME fort Calhoun Station DATE September 9, 1988 OOMPLEmo BY W. J. Blessie REPORTMONni AUGUST 1988 TELEPHONE (402) 536-4595
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.Ej j ca me a c.r sh 88-03 880816 5 0 H 4 N/A SD COND On August 16, 1988, power was further reduced (from 90% to 80%) due to an increase in river water temperature coupled with a poor performing ccnden-sor. This caused a further decrease in the cooling capabilities of the con-densor and is limiting the electrical output of the generator. The unit it remaining at 80%.
1 2 3 4 F-Forced Hessest essehet Esduinst G - besanscemme S-Sdiedded A-r e Feewe F=rd-sql 14eenuel for Preparemen et Desa 844mbulennaios er Test 2-teanuel Serasi Estery ha ser I h C-mesumans 3-Ameseisac Scrasi Event Report SSit fee peUflEG-OtS11 D-needesery neesseeman 4-oeher a-pa-me E-Operecer Treseis 8 Ucones re 5 F-Adubduereews Essissit 1 - Sesto Source Ghemenal Error 9tCoher Kapdebt tomt
Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending Auaust 1988 ,_
- 1. Scheduled date for next refueling shutdown. Seotember 1988
- 2. Scheduled date for res+. art 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?
- Change total planar radial peaking factor limit from 1.85 to 1.80
- Change core inlet temperature from 545'F to 543'F
- Clarification of LHR LCO
- Miscellaneous changes
- 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 schtduled?
1
- 4. Scheduled date(s) for submitting proposed 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 metiods, significant changes in fuel design, new operating procedures.
- 6. The number of fuel assemblies: a in the core 133 assembites 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 ein consolidation
- 7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994*
- Full core offload of 133 assemblies lost.
Prepared by da;- MM Date Auaust 25. 1988
~. .
i OMAHA PUBLIC POWER DISTRICT l
Fort Calhoun Station Unit No. 1 l
August 1988 Monthly Operations Report l
- 1. OPERATIONS SUWiARY I Fort Calhoun Station operated at 90% power until August 15 1988, when a powerreductionto80%wasinitiatedduetocontinuedproblemswith condenser efficiency and high river temperatures. Power remained at 80%
to conserve reactivity due to the extended shutdown date for the refueling outage. During August two operators and two engineers received Senior l
Reactor Operator licenses, and one operator received a Reactor Operator license. NRC inspections were performed in health physics addressing l outage preparation and dosimetry, Appendix R triennial inspection on fire protection and a five-man region closecut team for open items. The chemical control prograu was implemented.
l No safety valves or PORY challenges or failures occurred.
l A. PERFORMANCE CHARACTERISTIC:s None
- 8. CHANGES IN OPERATING METHODS None 1
C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS All tests and inspections were done on schedule with acceptable results.
D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COWilSS10N APPROVAL.
Procedure De script ion SP STROKE-1 In Service Testing of Air Operated, CQC Valves.
This procedure did not constitute an unreviened safety question as defined by 10CFR50.S9 because it only allowed stroke testing to be conducted on 38 air operated CQE valves. The objective of the testing is to determine if valve operability was degraded (or is degrading) due to the intrusion of water into the instrument air system. This testing did not in any way compromise plant
, safety, but enhanced it by ensuring operability of safety related valves.
l l
. . T '
MonthlyOperationsReport August 19o8 Page To D. CHANGES, TESTS AND EXPER:MENIS CARRIED OUT WITHOUT COMISSION APPROVAL (continued) :
System Acceptanca Comittee Packages for August 1988:
Packaqt Description / Analysis EEAR FC-86-010 QSPDS Software Changes. l t
This modification provided for new EPROMS for the QSPDS. This modification does not affect any safety analyses under Technical Specifications.
E. RESULTS OF LEAX RATE TESTS The leak rate test on the containment purge valves (penetrations M-87 andM-88)wascompletedonJuly 19, 1988, per ST-CONT-3, F.4. The "as found" and "as left" leak rates for penetrations M-87 and M-88 were all 0 secm. The test frequency of ST-CONT-3, F.4, has been increased as a result of the unsatisfactory "as found" leak rate of penetration M-87 during the December 1987 test of the containment purge vaives.
The "as left" *B" and "C" leak rate was 374.2 seem following the June 3, 1988, leak rate test. Since both sets of containment purge valves tested zero leakage during the July 19, 1988, test, the total leakage remains unchanged. This leak rate is well below the allowed leakage of 0.6 L aas specified in 10 CFR 50 Appendix J.
l F. CHANGES IN PLANT OPERATING STAFF l
Mr. Eugene Riggs received a Reactor Operators license. Mr. Carl {
Jensen and Mr. Robert luikens each received a Senior Reactor l Operators license. Mr. John Adams was promoted from Operations .
Engineer to Reactor Engineer. Mr. Jerry Shuck was promoted from !
Nuclear Production Engineer to Operations Engineer and received a j Senior Reactor Operators license. Mr. Jens Friedrichsen received a Senior Reactor Operators license.
l G. TRAINING f
During the month of August, notification was received that all five individuals sitting for the NRC license examinations passed (4 SR0's ,
and 1 RO). Work continued on preparation of Job Performance Measures *
(JPM's) and questions for the licensed requalification exam bank. :
l f
Monthly Operations Report August 1988 Page Three G. TRAINING (continued)
Non-licensed and licensed vperator requalification, STA requalification, and EONT training continued. Orientation training l was conducted for system engineers. The first half of technical ,
staff training was completed. The Su>ervisor-Chemistry and Radiation '
Protection Training has worked with tie Metropolitan Technical Community College to establish a degree program for Radiation r Protection Technicians. Effective August 1988, the Board of ;
i Governors of Metropolitan Technical Comunity College approved an I associate degree prog.am in Radiological Health Technology.
Radiation Protection Senior Technician contractors for the upcoming i refueling outage were screened by an entrancc examination prior to being accepted to work at the Fort Calhour. Station. Senior Technicians who failed to pass the entrance examination will not be allowed to work at Fort Calhoun Station. Two Chemistry instructors are rotating shifts with the Shift Chemistry Technicians to qualify and to improve the 0JT process. Maintenance training completed precutage administrative training for Central Maintenance personnel. ;
Observation Training has been taught continually through t1e month of !
August to qualify appropriate personnel prior to the outage. General Empiryee Training is providing additionci classes to handle outage '
personel.
H. CHANGli, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0mlSSION AUTHORIZATION PURSUANT TO 10CFR50.59 l
None II. K11NTENANCE(SignificantSafetyRelated) l See attached printout, i i yr N r'ilb h -
W. Gary Gates
>t Manager-Fort Calhoun Station l ;
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. 1 Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 September 15, 1988 LIC-88-718 U. S. Nuclear Regulatory Comission Document Control Oesk Mail Station P1-137 Washington, DC 20555
Reference:
Docket No. 50 '85 Gentlemen:
i
SUBJECT:
August Monthly Operating Report i
) Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),
please find enclosed one copy of the August 1988 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.
l
, Sincerely,
! /
) ,/j '//"
- L . orris Division Manager Nuclear Operations KJH/wjb
- Enclosures i et P. H. Harrell - NRC Senior Resident Inspector ,
NRC Regional Office <
i Office of Management & Program Analysis (2) l R. H. Caruso - Combustion Engineering
, R. J. Simon - Westinghouse l Nuclear Safety Analysis Center ,
INP0 Records Center I
] American Nuclear Insurers i
NRC File (FCS)
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