ML19253B568
| ML19253B568 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 10/10/1979 |
| From: | Hickle B OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML19253B567 | List: |
| References | |
| NUDOCS 7910160415 | |
| Download: ML19253B568 (7) | |
Text
.
AVERAGE DAILY UNIT POWER LEVEL s
50-285 DOCKET NO.
UNIT Fort Calhoun DATE Octnhor 10. 1979 COMPLETED BY B. J. Hickle TELEPl!ONE 402-536-441)_
MONTil September, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe Net) 1 47A 7 17 436.1 2
427.9 18 435.2 3
429.7 19 435.6 4
427 0 20 435.7 5
426.7 21 435.4 6
427.1 22 436.8 7
42R.5 23 436.9 8
428.7 24 437.6 9
411 I
.25 415.7 10 411 R 26 414 7 11 dan A 27 454.9 12 431.3 28 433.8 13 434.1 29 434.1 14 416 4 30 433.2 15 435.7 3g 16 415 7 INSTRUCTIONS On this format. list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
1154 149 WI77) 7910160
OPERATING DATA REPORT DOCKET NO. 50-285 DATE October 10, 1979 CONIPLETED BY B. J. Hickle TELEP110NE 402-536-4413 OPERATING STATUS
- 1. Unit Name:
Fort Calhoun Station Unit No. 1 N"te5
- 2. Reporting Period.
September, 1979
- 3. Licensed Thermal Power (51Wt): ___l420
- 4. Nameplate Rating (Gross SIWE):
502
- 5. Design Electrical Rating (Net 51We): 457
- 6. Stasimum Dependable Capacity (Gross 51We): 48l
- 7. 51asimum Dependable Capacity (Net alWe):
457
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Give Reasons:
N/A
- 9. Power Lesel To Which Restricted. lf Any (Net 51We):
N/A
- 10. Reasons For Restrictions.If Any:
N/A This 51onth Yr..to Date Cumulative II. Ilours in Reporting Period 720.0 6_551.0
'52.728.0
- 12. Number Of flours Reactor Was Critical 720.0 6.506.5 42,471.5
- 13. Reactor Reserve Shutdown flours 0.0 0.0 1.136.0
- 14. liours Generator On-Line 720.0 6,466.5 41,532.6
- 15. Unit Resene Shutdown flours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (51Wil) 1.013.878.5 8.936,526.3 50,584,949.6
- 17. Grow Electrical Energy Generated (51Wil) 327&_M _. 2.980.059.9 16.784.321.6 Iti. Net Electrical Energy Generated (31Wil) 311.612.1 2,833,379.5 15,854,785.2
- 19. Unit Senice Factor 100.0 98.7 78.8
- 20. Unit Availability Factor 100.d _
98.7 78.8
- 21. Unit Capacity Factor (Using SIDC Net) 44 7 44_6 66.4
- 22. Unit Capacity Factor (Using DER Net) 94.7 94.6 65.8
- 23. Unit Forced Outage Rate 0.0 1_3 4.4
- 24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date.and Duration of Each):
.lanuary 1. 1980 - Refueling Outage - Two Month Duration October 26, 1979 - Inspection of S.G. to Piping Welds - Approximately Ten Days
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: _J /A
- 26. Units in Test Status lPrior to Commercial 0peration):
Forecast Achiesed INilI A L CRITICA LITY IN111AL ELECTRICITY CO\\1\\1ERCI AL OPER ATION 11$.1 i50
<"/77)
jD h
r e
6 Z
m, m..
a vsm "r,c
- 2. R
- z E. o-9 n
a m
a2n u
1
=.O. m. m.c. o. m. >. x Ty.pe o.o >. o x x r.m.
- c c 2 o a wc=
sif 2 3 O T c 5' E. S
- E 5' E z;- 2. g'3 gEag5g Durat. ion 4. D -4 Q " g E (Hours)
' r,7' E. x
- T S
" " 3. 0
- 5. E:
~E S E.
HC vg 2a Reason 3 c
m
.x r.a
.o.-
.x c.
o E.
6 Er Method of E
5 Shutting E
ghD Down Reactor 3
- 'i M
x 0-6 m
C m
-4 E-x r-o e
4 75' x
o
=
cn o A
t Eg v
2 a
a o
x z
dr 2
w c
- gv m
P""~E System x
@i E E O.
Code 4 g
5 5
3 3 0 3
- 5. 5. a-N
- 5..
7 m
ME C/)
C 5 8' Q Component C
-mu n
"aB Code 5 3-e" d
e o2m
- s 4s n
7 O
e
- 4 *'3 0
m ommmm a
S o
c m
y
-g
~
- m" E c.
=>a rF Z
n e
en-
= ~
m MN E
x m,3 E
~CS u
xO qH m
C >o 2 H
n 3-n -
3uO
- e. me h
o m -< s r 2 cat
- c zm m
m m.o e
- g' ~
3-R
=
-F3 m
C.
F" c"
Q g
bComm MF9N C
0 0
0 xEC.
N r+ 7 e
" awe e
c-o c+ N r.
T3 G3 U,
e CT CD 4
LE W
O O U1
- m C,r.I.
1 Cu b
O "
3 0
4 7'" OO
~
-a C
m W G 3
O c"
^
Ne g
Refueling Infornution Fort Calhoun - Unit No. 1 Report for the nonth ending September 30. 1979.
1.
Scheduled date for next refueling shutdown.
January 1, 1980 2.
Scheduled date for restart following refueling.
March 1, 1980 3.
Will refueling or resunption of operation thereaf ter require a technical specification change or other license anund: Tent?
Yes If answer is yes, what, in general, will a.
these be?
Stretching power to 1500 fiWth is planned in conjunction with the change in fuel supplier to Exxon.
b.
If answer is no, has the reload fuel design and core configuration been revieaed 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?
Stretch Power Application 4.
Scheduled date(s) for submitting proposed licensing
-Site Related Information, action and support formation.
July, 1979 - Submitted
-Core Related Analysis 5.
Inportant licensi. 3 considerations associated with and Tech. Spec. Changes, refueling, e.g., new or different fuel design or November, 1979 supplier, unreviewed design or performance analysis nothods, significant changes in fuel design, nea operating procedures.
First use of Exxon fuel in Fort Calhoun.
Stretching power from 1420 filth to 1500 fUth.
6.
The nu:rber of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483 7.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1985 M_
Date October 3,1979 Prepared by
/
llS4 152
CMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No, 1 September 1979 Monthly' Operations Report I.
OPERATIONS
SUMMARY
Fort Calhoun operation continued at essentially 100% power for the month of September. No significant power reductions occurred during the =onth of September.
The change to ec=plete six shift operation was completed durin6 the conth of September. This change vil] allow the entire shift to devote one week in six to training.
Preparations for a potential unit outage in late October continued.
The operations staff participated in the review of fire protection todifications, response to several NRC information requests and the implementation of Three Mile Island reco==endations.
A Nuclear Regulatory Cor: mission audit was conducted during Septe=ber with no ite=s of nonec=pliance identified in the operations area.
The employ =ent of a fire watch team made up of part-time personnel is continuing with the tre.ining of initial fire watch team members to begin in early October.
Fort Calhoun operations is participating in radiation protection refresher courses during the month of September.
A.
PERFORMANCE CHARACTERISTICS LER Number Deficiency NONE B.
CHRIGES IN CPERATING METHODS NONE C.
RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B, vere performed in accordance with the ennual surveillance test schedule.
The following is a su==ary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:
Operations Incident Deficiency OI-839 ST-ERM Lost = ilk sa=ples J J s,4 c
cis3
8 Monthly Operations Report September 1979 Page Two E
CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description MR FC-78-52A Site Cc=pletion Report for Halon System for Control Room Walk-in Cabinet / completed as designed.
SP-FAUD-1 Fuel Assembly Uplift Detection Test - c11 loopa indicate sufficient assurance of re-quired dowward force on fuel assemblies.
SP-VA-80 Hydrogen Purge System Test - operability of the Hydrogen Purge System verified.
SP-RPS-5 Excore Detector Sy= metric Offset Recalibration/
all results nor=al.
MR FC-79-13 Warehouse Sprinkler Addition / completed as designed.
M.0. 1661 EHC Jumper to eliminate trip on loss of 125 V.D.C./ completed as designed.
M.0. 65 Ground PR's/ completed as designed.
E.
RESULTS OF IZAK RATE TESTS NCNE F.
CHANGES IN PLANT OPERATING STAFF NONE G.
TRAINING Training included operations training on radiation protection at Fort Calhoun Station, vaste disposal, potable water and emer6ency procedures. Plant maintenance received training on vaste disposal systems and packaging and solenoid valve training.
Radiation protection classes vere held for District personnel and contract personnel.
H.
CHANGES,."C'"3 AND EXPERIEITS REQUIRING NUCLEAR REGULATORY COMMISSICN AUTHORIZATION PURSUANT TO 10CFR50.59 NONE
}
\\
\\
f Wt-Uv\\ )C Approved by
{'
anager-Fort Calhoun Station irs 4 iS4
Menthly Operations Report September 1979 Page Three II. MAIITE'iMICE (Significant Safety Related)
Ccrrective Action I M. O. #
Date i
Description 20622 9-11-79 FH-12 Adjust and inspect trolley /
bridge drive 1612 9-13-79 CH hA Bottle oiler on the pump is Replaced oil seals leaking 2009 9-18-79 CH-1B Packing Leak Replace packing 1998 9-17-79 RWH-86, RWH-97 has 1cose clevis Tightened one elevis and shortened the other.
1999 9-17-79 RWH-100 nissing 1/2" nut on Replaced nut clevis IiS4 i55