ML20153C695
| ML20153C695 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/31/1986 |
| From: | Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT |
| To: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| LIC-86-067, LIC-86-67, NUDOCS 8602210512 | |
| Download: ML20153C695 (10) | |
Text
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AVER AGE DAILY UNIT P0hER LEVEL DOCKET NO.
50-285 UNil Fort Calhoun Station DATE February 10. 1986 T.P. Matthews COMPLET ED ilY s
402-536-4733 TELEPilONE January, 1986 MONTH DAY AVERAGE DAILY POWER LEVLL DAY AVER AGE DAILY PO%ER LEVEL ptwe. Net )
(MWe-Neu 0.0 17
!!! 7 2
0.0_
is 12n a 0.0 121.2 3
39 4
0.0 20 17n 2 5
0.0 21 124 1 6
0.0 r
124 r, 0.0 23 125.4 7
0.0 g
24 125.0 0.0 127.0 9
25 10 n.n 26 127 r, 0.0 126.7 is 2;
0.0 127.0 12 23 i3 0.0 29 124.1 34 0.0 3o 125.1 0.0 3:
123.7 is 38.2 is INSTRUCTIONS On this format. list the a$erage daily unit power leset in Mwe Net for each day in the reporting m.mth. Compute to the nearest whole nwgawatt.
19I771 maaggajtggagg.
1e 2<
$/ i
OPERATING DATA REPORT DOCKET NO.
50-285 DATI: Februarry_J0, 1986 CONIPLE1ED tlY T Ma ws 3
1 FLEPilONE OPERATING STATUS N"
- 1. Unit Name: Fort Calhoun Station
- 2. Reporting Period:
January, 1986
- 3. Licensed 1hermal Power tMwt):
1500
- 4. Nameplate Rating (Grow Mher 502 478
- 5. Design Electrical RatingiNet MWe):
502
- 6. Masimum Dependable Capacity IGron MWe):
478
- 7. Masimum Dependable Capacity (Net MWe)
- h. If Changes Occur in Capacity Ratings titems Number 3 t hrough 7) Since Last Report.Gise Reasont N/A
- 9. Power Leiel To which Restricted,if Any (Net Mbe)
N/A
- 10. Reasons For Restnctions. If Any:
Nnnn This Month Yr.-to Date Cumulatise 744.0 744.0 108,290.0
- 11. floun in Reporting Period 548.5 548.5 82,294.8
- 12. Number Of II.mts Reactor wa, critical
- 13. Reactor Resene Shutdown flour, 0.0 0.0 1.309.5
- 14. Ilours Generator On-Line 372.7 372.7 81.495'.6
- 15. Unit Resene Shutdown floun 0.0 0.0 0.0 174,509.6 174,509.6 103,925,554.2
- 16. Grow Thermal Energy Generated (MWil) 17 Grow Electrical Energy Generated (Mbil, 50,968.0_ _
50,968.0 34.035,537.0_.
45,548.3 45,548.3 32,523,441.7 IV Net Elettncal Energ> Generated (Mwit,
- 19. Lnit Senice Factor 50.1 50.1 75.3 50.1 50.1 75.3
- 20. Unit As.nlahihty I acto,
- 21. Unit Capacity Factor (Using MDC Neti 12.8 12.8 65.2
- 22. Unit Capacity ractor iUsing DLR Net:
12.8 12.8 63.1
- 23. Unit Forced Outage Rate 0.0 0.0 3_5 24 Shutdowns Scheduled User Nest 6 Months (1.spe. Date.and Duration of Fach t None 2.4. If Shut Down At End Of Report Penod. Lstimated Date of Startup.
N/A
- 26. Units in test Status tPrior to Commercial Operationi iorecast Ac inesed INill \\ L CRI flCAl.11 Y N/A INiil \\ L f Li C1RICI f Y CO\\l\\ll RCl \\l. Ol'l R \\ IlON (9/77i
l i
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO.
50-285 UNIT N AM E Fort Calhnun Station UATE February.LO.
1986 COMPT.E RD BY T. P. Ffatthews REPORT MONIH Januarv. 1986 TELErilONE 402-536-4733 E
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3 j Ei IAensee h
h Cause & Currective No.
Date e-
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Event u7
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Action to O
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d-Report :
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Present Recurrence d
l 85-01 850928 S
2641.5 C
1 N/A XX XXXXX 1985 refueling outage commenced on September 28, 1985.
The unit came back on line January 16, 1986.
l l
l I
2 3
4 F: For ed Reaum
\\tethod:
Edubit G. Instiustnms s
S-Schediated A-Eqmpment Fatfure t Esplame i Manual for Prepararam of Data -
B Maintenance or Test 2-Manual Scram.
Entry Sheets for LNensee C-Refuehng
.t. Automatu-Scram.
Esent Repor 1.1 R t Fife (NURI G D Regulatory RestrAtmn 40ther i E splam t 0161)
I. operator Trammgi tuenw Eummarron F-Ad minrst rain e 4
G-Operatamal I r ror I E spi,sm i I shibat 1 - Same Sour.e 19I77)
It Other el splaini
Refueling Information Ebrt Calhoun - Unit ib.1 Pcport for the ntnth ending January 1986 1.
Scheduled date for next refueling shutdown.
March 1987 2.
Scheduled date for restart folicwing refueling, liay 1987 3.
Will refueling or restription of operation thereaf ter require a technical specification change or other license anendrent?
Yes a.
If answr is yes, what, in general, will these be?
Fuel supplier change from EilC to CE and possible Technical Specification
- chanou, b.
If answer is no, has the reload fuel design and core configuration been reviewn! by your Plant Safet/ Review Cbemittee to deter-ntine whether any unreviewed safety questions are associated with the core reload.
c.
If rn such review has taken place, when is it scheduled?
j 4.
Scheduled date(s) for submitting proposed licensing action and support information.
February 1987 5.
Inportant licensing considerations associated with refteling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes in fuel design, new operating procedures.
Ilew fuel supplier (Combustion Engineering) but the new fuel will be essentially the same as that supplied by Combustion Engineering for Cycle 5.
6.
The number of fuel assenblies: a) in the core 133 asserblics b) in the spent fuel pool 348 i
c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased j
storage capacity via funi nin consolidation 7.
'Ihe projected date of the last refueling tlat can in dischartJed to the spent fuel pool assuming t1m present i
licensed capacity.
1996 l
l Prepared by_
h ce4MI Date_
February 4,1986 V
l
\\
L
OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit flo. 1 January, 1986 Monthly Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun Station completed plant heatup on January 6, 1986.
The reactor was taken critical for Cycle 10 on January 9, 1986.
Low power physics tests lasted three days.
After getting secondary chemistry in specification for the 5% power holdpoint, the generator was put on-line January 16, 1986, and power was raised to 30%, where another chemistry holdpoint was satisfied.
For the first time, injection of boric acid into the steam generator secondary was performed to reduce the corrosion process which causes tube denting.
Secondary boric acid levels were kept at approximately 50 ppm for a 96-hour soak and will be maintained at 5 to 10 ppm for the remainder of Cycle 10.
Accelerated training continued for the seven licensed i
operators who failed the 1985 requalification examinations, Normal training continued for licensed and non-licensed i
operator requalification, auxiliary operator and equipment operator.
A vendor cource was given for chemistry techni-l clans.
Training was completed on the new Emergency Operating Procedures (EOP's).
t No safety valve or PORV challenges or failures occurred.
A.
PERFORMA!!CE CHARACTERISTICS None B.
CHAtlGES Ili OPERATIliG METHODS lione C.
RESULTS OF SURVEILLAliCE TESTS AllD IllSPECTIOliS fione I
)
Monthly Operations Report January, 1986 Page Two D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure DescriptioD SP-VA-80 Hydrogen Purgo System Test.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure only checks operability of fans and cleanliness of the filters.
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-UF6-1 Uranium Hexaflouride Storage Cylinder External Visual Inspection.
This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the inspection and verification of integrity of UF6 storage containers.
System Acceptance Committee Packages for January, 1986:
P_ackace R9scIlntionZAnalysis EEAR FC-85-23 Installation of Radiant Energy Shields.
This modification provided for the installation of radiant energy shields betwoon certain pieces of equipment which previously did not meet the separation requirements set forth in 10CFR50 Appendix R.
This modification does not have an adverse effect on the safety analysis.
Monthly Operations Report January, 1986 Page Three D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT CO!CIISSION APPROVAL (continued)
System Acceptance Committee Packages for January, 1986 (continued)
Pack _ age Descript LoJL/ Analysi.s EEAR FC-83-158 Air Accumulators for YCV-1045A&B.
This modification provided for the addition of air accumulators to YCV-1045A&B.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-85-199 Condensate Bypass Valve Replacement.
This modification replaced 6 of the Crane 1" bypass valves in he condensate system with different style valves.
The Crane valves have been high maintenance items.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-85-198 Installation and Testing Procedures for LCV-1199.
This modification provided for the replacement of LCV-1199 valve body from carbon steel to 316 stainless steel.
Two-phase flow eroded the original carbon steel body.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-83-90 Low Pressure Feedwater Heaters Tube Bundles and Drain Coolers.
This modification changed copper nickel tubes to stainless steel tubes in low pressure feedwater heaters lA/2A, 1B/2B, 3A, 3B and drain coolers lA and IB.
This modification does not have an adverse effect on the safety analysis.
(
Monthly Operations Report January, 1986 Page Four D.
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)
System Acceptance Committee Packages for January, 1986 (continued)
Package Dgsgription/Analysin EEAR FC-84-197 Feedwater Blowdown Piping Erosion.
This modification provided for the installation of manual isolation valves "or !!CV-1389 & 1390 and relocation next to the blowdown tank to prevent pipe erosion from two-phase flow.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-85-24 Rerouting Cables in Containment.
This modification rorouted cables for redundant pressurizer level transmitters (LT-10lX and LT-101Y) and for pressurizer spray valves HCV-240 and !!CV-249 to ensure the fire protection criteria of 10CFR50 Appendix R is mot.
This modification does not have an adverse effect on the safety analysis.
EEAR FC-85-200 MSIV Single Failure Mode.
This modification ensured no single failure of MSIV control circuitry would cause inadvertent closing of the Main Steam Isolation Valves.
This modification does not have an adverse effect on the safety analysis.
E.
RESULTS OF LEAK RATE TESTS The Type A leak rate report is currently being reviewed and will be submitted under separate cover.
The Type B and C leak rate results will be submitted in the February Monthly Operations Report.
8 t
Monthly Operations Report January, 1986 Page Five F.
CHANGES Ili PLANT OPERATING STAFF
!!r. Steve J.
Willrett was appointed Supervisor -
Administrative Services and Security offective on January 16, 1986.
G.
TRAINING Accelerated training continued for the seven licensed operators who failed the 1985 requalification examinations.
Normal training continued for licensed and non-licensed operator requalification, auxiliary operator and equipment operator.
A vendor course was given for chemistry technicians.
Training was completed on the new Emergency Operating Procedures (EOP's).
H.
CHANGES, TESTS AllD EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSIO!! AUTHORIZATION PURSUANT TO 10CFR50.59 AratLdmat_lL%.
Description
!!o. 94 The amendment changes the reactor vessel materials surveillance capsule removal schedule.
II.
MAINTENA!!CE (Significant Safety Related)
A report of all significant maintenance performed during the 1985 refueling outage will be submitted in the February Monthly Operations Report.
4(/. /
A W. Gary atos Manager Fort Calhoun Station i
l Omaha Public Power District 1623 Harney Omaha Nebraska 68102 2247 402/536 4000 February 13, 1986 LIC-86-067 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. fluclear Regulatory Commission Washington, D.C. 20555
Reference:
Docket tio. 50-285
Dear Mr. Taylor:
January Monthly Operating Report Please find enclosed ten (10) copies of the January, 1986 Monthly Operating Report for the Fort Calhoun Station Unit tio. 1.
Sincerely, k f, e l b R. L. Andrews Division Manager fluclear Production RLA/TPM/me Enclosures cc: flRC Regional Office J
Office of Management & Program Analysis (..
l Mr. R. R. Mills - Combustion Engineering Mr. R. J. Simon - Westinghouse fluclear Safety Analysis Center l
IllP0 Records Center America-fluclear Insurers f4RC File i
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