ML19338D496: Difference between revisions
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:, . 7 AVERAGE DAILY UNIT POWER LEVEL | :, . 7 AVERAGE DAILY UNIT POWER LEVEL | ||
. DOCKET NO. 50-285 | . DOCKET NO. 50-285 | ||
. 3.iT | . 3.iT Fort Calhoun #1 DATE September-8,~1980 CONSPI.ETED BY ~B. | ||
Fort Calhoun #1 DATE September-8,~1980 CONSPI.ETED BY ~B. | |||
J. Hickle TELEPIIONE _(402)536-4413 MONE August, 1980 , | J. Hickle TELEPIIONE _(402)536-4413 MONE August, 1980 , | ||
' DAY AVERAGE DAILY POWER LEVEL DAY. AVER AGE DAILY POWER LEVEL t- . (MWe-Net) (MWe-Net) 434 37 435 2 433 is 435 | ' DAY AVERAGE DAILY POWER LEVEL DAY. AVER AGE DAILY POWER LEVEL t- . (MWe-Net) (MWe-Net) 434 37 435 2 433 is 435 3 433 39 432 4 434 20 432 3 434 21 431 6 434 22 431 7A. 433 23 434 | ||
3 433 39 432 4 434 20 432 3 434 21 431 6 434 22 431 7A. 433 23 434 | |||
: s. 431- 24 435 9 431 25 435 to '432 26 433 | : s. 431- 24 435 9 431 25 435 to '432 26 433 | ||
.ti 433 27 _ | .ti 433 27 _ | ||
434 | 434 L12. 433~ 28 . | ||
L12. 433~ 28 . | |||
437 13 '433 29 436-14- 434- 30 435 i' | 437 13 '433 29 436-14- 434- 30 435 i' | ||
-- 15 ; 434 3 435 a | -- 15 ; 434 3 435 a | ||
\ | \ | ||
Line 58: | Line 41: | ||
g , ; _ | g , ; _ | ||
g-= . | g-= . | ||
m y < -c.. | m y < -c.. | ||
x' | x' 4 | ||
1 / | |||
OPERATING DATA REPORT | OPERATING DATA REPORT | ||
: DOCKET NO; 50-285- ~ | : DOCKET NO; 50-285- ~ | ||
' DATE Septemoer 8,' 1980 ' | ' DATE Septemoer 8,' 1980 ' | ||
COMPLETED BY- B. J. Hickle . | COMPLETED BY- B. J. Hickle . | ||
: TELEPilONE (402)53T-4413 | : TELEPilONE (402)53T-4413 | ||
> OPERITING STATU} | > OPERITING STATU} | ||
FortiCalhoun #1 Notes I. Unit Name: | |||
FortiCalhoun #1 Notes | |||
I. Unit Name: | |||
- 2. Reporting Period:. -August, 1980-2 3. Licensed Thermal Power (MWt): | - 2. Reporting Period:. -August, 1980-2 3. Licensed Thermal Power (MWt): | ||
1420 | 1420 | ||
Line 80: | Line 56: | ||
: 5. Design Electrical Rating (Net MWe):. 457 | : 5. Design Electrical Rating (Net MWe):. 457 | ||
: 6. Maximum Dependable Capacity (Gross MWe)': 401 | : 6. Maximum Dependable Capacity (Gross MWe)': 401 | ||
'457 | '457 7/ Maximum Dependable Capacity (Net MWe): | ||
7/ Maximum Dependable Capacity (Net MWe): | |||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons: | : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons: | ||
N/A | N/A | ||
Line 98: | Line 72: | ||
: 16. Gross Thermal Energy Generated (MWH) 1,049,152.6 3,166,746.3: 56,401,725.6- . | : 16. Gross Thermal Energy Generated (MWH) 1,049,152.6 3,166,746.3: 56,401,725.6- . | ||
: 17. Gross Electrical Energy Generated (MWH) 339.426.0 1.027,932.0 _18,688,161.6 18.- Net Electrical Energy Generated (MWH) 322,571.2 974,199.0 17,661,718.8 . | : 17. Gross Electrical Energy Generated (MWH) 339.426.0 1.027,932.0 _18,688,161.6 18.- Net Electrical Energy Generated (MWH) 322,571.2 974,199.0 17,661,718.8 . | ||
: 19. . Unit Senice Factor 100.0- 40.8 75.4- | : 19. . Unit Senice Factor 100.0- 40.8 75.4-20." Unit A'vailability Factor ; 100.0 40.8- : 75.4 . | ||
20." Unit A'vailability Factor ; 100.0 40.8- : 75.4 . | |||
. 21. Unit Capacity Factor (Using MDC Net) . - 94.9__ 36.4 64.0- g 22.' Unit Capacity Factor (Using DER N'et) . 94.9- 36.4 63.6 23.' Unit Forced Outage Rate 0.0 0.4 - | . 21. Unit Capacity Factor (Using MDC Net) . - 94.9__ 36.4 64.0- g 22.' Unit Capacity Factor (Using DER N'et) . 94.9- 36.4 63.6 23.' Unit Forced Outage Rate 0.0 0.4 - | ||
4.3 | 4.3 | ||
Line 107: | Line 79: | ||
~ | ~ | ||
Nnno - | Nnno - | ||
i.. | i.. | ||
* L . - | * L . - | ||
Line 115: | Line 85: | ||
? 25. If Shut'Down At End Of Report Period. Estimated Da' te of Startup: | ? 25. If Shut'Down At End Of Report Period. Estimated Da' te of Startup: | ||
k 26. Units in Test Status (Prior to Commercial Operation): | k 26. Units in Test Status (Prior to Commercial Operation): | ||
Forecast Achieved INITIAL CRITICALITY . -> | |||
Forecast Achieved | |||
INITIAL CRITICALITY . -> | |||
INITIAL ELECTRICITY | INITIAL ELECTRICITY | ||
- ~, COMMERCI L OPERATION - | - ~, COMMERCI L OPERATION - | ||
0 - | 0 - | ||
;(4/77) p 1 a e < , | ;(4/77) p 1 a e < , | ||
~ - - - | ~ - - - | ||
m 6 em 7 | |||
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.g ?- . | .g ?- . | ||
n w mm .?. . | n w mm .?. . | ||
Mn f | Mn f | ||
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i m | i m | ||
Line 161: | Line 115: | ||
:s n ". * | :s n ". * | ||
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E Re.ison-m M .- - ~^ | |||
m x | m x | ||
y.. c. D rc .x | y.. c. D rc .x a | ||
a | |||
'.d. d Er Method of : | '.d. d Er Method of : | ||
E E 5 Shutting @ | E E 5 Shutting @ | ||
Line 176: | Line 124: | ||
e , z. | e , z. | ||
E m C E x r- -3 -$O 3 | E m C E x r- -3 -$O 3 | ||
4?W en 3 .3.< E Eg 'g 2 | 4?W en 3 .3.< E Eg 'g 2 88 - " o > | ||
88 - " o > | |||
z 2 w Yr C o | z 2 w Yr C o | ||
> O P W.J 7 E System c | > O P W.J 7 E System c | ||
Line 184: | Line 130: | ||
.cu u :r | .cu u :r | ||
-~n ~ | -~n ~ | ||
c | c n | ||
QCg c& w g n= E. E. - g | |||
. m mE t/3 0 | . m mE t/3 0 | ||
. --5 E Q - ComEonent - | . --5 E Q - ComEonent - | ||
Line 194: | Line 139: | ||
u A O | u A O | ||
? | ? | ||
f g") | f g") | ||
ommmm m | |||
ommmm | x- --e=;x. | ||
a- H m ., ' . c - | a- H m ., ' . c - | ||
=~ @O :" 4 , | =~ @O :" 4 , | ||
Line 206: | Line 147: | ||
~' | ~' | ||
. .~ ~ x g 5 ~S> -@H.-HM. | . .~ ~ x g 5 ~S> -@H.-HM. | ||
x !d c ~ W ii' _gm | x !d c ~ W ii' _gm y,' | ||
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.g x e a c2E- -c n=o- c | .g x e a c2E- -c n=o- c | ||
:- o e >gg2.,- Q. | :- o e >gg2.,- Q. | ||
Line 223: | Line 162: | ||
a WI C" Os Y m. (D - | a WI C" Os Y m. (D - | ||
e n 1 3 C bx o x | e n 1 3 C bx o x | ||
m b" m C | m b" m C | ||
>=*(D e 3 0. | >=*(D e 3 0. | ||
_ W | _ W | ||
~ m | ~ m | ||
Line 232: | Line 169: | ||
C3 a .K | C3 a .K | ||
; O :: \ | ; O :: \ | ||
v t F , , ,$ _ 1 | |||
v t | |||
F , , ,$ _ 1 | |||
-L | -L | ||
. - - - - ~ '- ' - | . - - - - ~ '- ' - | ||
Line 244: | Line 176: | ||
~ - | ~ - | ||
; _ | ; _ | ||
7- v | 7- v | ||
;q k | ;q k | ||
~ | ~ | ||
(' . | (' . | ||
( - | ( - | ||
f Refuclingilnihr.etition = | f Refuclingilnihr.etition = | ||
- Fort ^Calhoun?--Unit No. 1 . | - Fort ^Calhoun?--Unit No. 1 . | ||
; Reportifor1the''nonth' ending August 31,l1980 .- . | ; Reportifor1the''nonth' ending August 31,l1980 .- . | ||
1.J Scheduled <date for nes:t' refueling. shutdown. :' September-15,-1981 | 1.J Scheduled <date for nes:t' refueling. shutdown. :' September-15,-1981 | ||
Line 267: | Line 190: | ||
-licenseJanendment? | -licenseJanendment? | ||
, ' a.: ; If' answer is yes, what, ~in general,;will | , ' a.: ; If' answer is yes, what, ~in general,;will | ||
.these be?' | .these be?' | ||
: b. 'If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unreviewed safety. questions NO are associated withLthe core reload. | : b. 'If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unreviewed safety. questions NO are associated withLthe core reload. | ||
- c. If no such review has.taken place, when is September 1,'1981 it scheduled? | - c. If no such review has.taken place, when is September 1,'1981 it scheduled? | ||
: 4. Scheduled-date(s)" for submitting proposed licensing : | : 4. Scheduled-date(s)" for submitting proposed licensing : | ||
action ~and support information. | action ~and support information. | ||
~5. Important licensing considerations associated with refueling, e.g. , inew or different fuel design or supplier, unroviewed design or performance analysis nethods, significant changes in fuel design, new | |||
~5. Important licensing considerations associated with refueling, e.g. , inew or different fuel design or | |||
supplier, unroviewed design or performance analysis nethods, significant changes in fuel design, new | |||
- operating procedures. . | - operating procedures. . | ||
k | k | ||
: \ | : \ | ||
+ | + | ||
133 assemblics | 133 assemblics | ||
: 6. We ntmber of fuel assenblies: a) in the core | : 6. We ntmber of fuel assenblies: a) in the core | ||
~ | ~ | ||
b) in the spent-fuel pool 197 c): spent' fuel pool' " | |||
. rstorage capacity 483 d)-planned spent fuel' pool * " | |||
b) in the spent-fuel pool | ' storage capacity 483 7.' l'Ihe projected ~datefof: the. last refueling that can be discharged'to ;thejspentifuel pool'asstnting the present 1985 Llicensed capacityn EMM . September 5,E1980 | ||
197 | |||
c): spent' fuel pool' " | |||
. rstorage capacity 483 | |||
d)-planned spent fuel' pool * " | |||
' storage capacity 483 7.' l'Ihe projected ~datefof: the. last refueling that can be discharged'to ;thejspentifuel pool'asstnting the present | |||
1985 Llicensed capacityn EMM . September 5,E1980 | |||
~ ' | ~ ' | ||
< <? Prepared'by . | < <? Prepared'by . | ||
Datc~ | Datc~ | ||
l :(/ - | l :(/ - | ||
Eg n | Eg n | ||
- f~ ' ' , W., | - f~ ' ' , W., | ||
r | r | ||
'Y w t r m. + | |||
'Y w t | |||
r m. + | |||
OMAHA- PUBLIC POWER DISTRICT . | OMAHA- PUBLIC POWER DISTRICT . | ||
Fort:Calhoun. Station Unit'No.'1 | Fort:Calhoun. Station Unit'No.'1 | ||
' August 1980 _. | ' August 1980 _. | ||
J Monthly Operations Report | J Monthly Operations Report I. OPERATIONS'SUMARY Fort Calhoun Station' received a license amendment during the month-Lof August which: allowed an. increase 1:s power level'to 1500 MWth. The operations department participated in the review of the operational-readiness of Fort-Calhoun~ Station to increase power-level. Plant | ||
I. OPERATIONS'SUMARY Fort Calhoun Station' received a license amendment during the month-Lof August which: allowed an. increase 1:s power level'to 1500 MWth. The operations department participated in the review of the operational-readiness of Fort-Calhoun~ Station to increase power-level. Plant | |||
. specific: training was given the Fort Calhoun staff on the expected | . specific: training was given the Fort Calhoun staff on the expected | ||
. s,r.. tem parameter: and procedure changes which vere required to implement | . s,r.. tem parameter: and procedure changes which vere required to implement | ||
Line 346: | Line 224: | ||
Normal surveillance tests and operational tests were completed with no abnormal results reported. | Normal surveillance tests and operational tests were completed with no abnormal results reported. | ||
The unit operated at a nominal 1h20 MWth during the month of August. | The unit operated at a nominal 1h20 MWth during the month of August. | ||
Normal six shift training continued during August. | Normal six shift training continued during August. | ||
A. . PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 80-012: During performance of ST-RPS-3, F.2, it was discovered that Trip Unit #3 (Reactor Coolant Flow) trip setpoints had drifted,out of specifi-cation in the nonconservative direction. Main-tenance: order #6405 was written to investigate the drift. The R.P.S. was immediately placed in a two-out-of-three logic to trip mode. | A. . PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 80-012: During performance of ST-RPS-3, F.2, it was discovered that Trip Unit #3 (Reactor Coolant Flow) trip setpoints had drifted,out of specifi-cation in the nonconservative direction. Main-tenance: order #6405 was written to investigate the drift. The R.P.S. was immediately placed in a two-out-of-three logic to trip mode. | ||
Technical Specification 1 3(2) applies. | Technical Specification 1 3(2) applies. | ||
LER-80-013 During normal power' operation it-vas noted that , | LER-80-013 During normal power' operation it-vas noted that , | ||
-Channel AJDC. sequencer SI-1 had a de-energized "on-auto" light associated with AC-3A, or the i safeguards equipment supplied 1from Bus 133B. | -Channel AJDC. sequencer SI-1 had a de-energized "on-auto" light associated with AC-3A, or the i safeguards equipment supplied 1from Bus 133B. | ||
.The'AC sequencer.for. channel A relatra safeguards | .The'AC sequencer.for. channel A relatra safeguards | ||
. equipment remained-operable throughout the event as were the. channel B AC and'DC sequencers. .The safeguards loads from all h80 volt equipment, except 1B3B associated equirment (which is AC-3A | . equipment remained-operable throughout the event as were the. channel B AC and'DC sequencers. .The safeguards loads from all h80 volt equipment, except 1B3B associated equirment (which is AC-3A | ||
.only) remained operable from the DC channel A sequencer SI-1. | .only) remained operable from the DC channel A sequencer SI-1. | ||
' t k | |||
b. | |||
' t | P. 5 I | ||
P. 5 | |||
I | |||
, yn .. | , yn .. | ||
~ .. | ~ .. | ||
a <- . . | a <- . . | ||
kk .. p > . | kk .. p > . | ||
Q '' | Q '' | ||
~ | ~ | ||
LMonthly< Operations (Report-IAugust.1980' | LMonthly< Operations (Report-IAugust.1980' i | ||
i | |||
iPage Two | iPage Two | ||
;- | ;- | ||
I ' A .' | I ' A .' | ||
PERFORMANCE CHARACTERISTICS (Continued) | PERFORMANCE CHARACTERISTICS (Continued) | ||
-LER Number ~ . _ Deficiency . | -LER Number ~ . _ Deficiency . | ||
'LER 80-01h : Transformer -(Th) of DG-r failed. This transformer fed power ;to .the diesel's oil' immersion heater as v ell as.; alarm circuitry; corresponding to _the following items: lLov. lube oil; pressure, lov lube oil level,2and.High orJLov lube oil' temperature. | 'LER 80-01h : Transformer -(Th) of DG-r failed. This transformer fed power ;to .the diesel's oil' immersion heater as v ell as.; alarm circuitry; corresponding to _the following items: lLov. lube oil; pressure, lov lube oil level,2and.High orJLov lube oil' temperature. | ||
During the time of the transformer. (Th) failure,- | During the time of the transformer. (Th) failure,- | ||
Line 415: | Line 265: | ||
* EEAR(FC-79-166- LCV-2 Replacement / completed per procedure. | * EEAR(FC-79-166- LCV-2 Replacement / completed per procedure. | ||
, e | , e | ||
'l-j 1l j- y sy - | |||
'l-j | |||
1l j- y sy - | |||
y; x - | y; x - | ||
.- , m - - | .- , m - - | ||
y | y | ||
;s . . . | ;s . . . | ||
r | r | ||
Line 438: | Line 275: | ||
Page Three D. LCHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL'(Continued) | Page Three D. LCHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL'(Continued) | ||
: Procedure Description-DCR 743-33 -Replacement of. Component Cooling Heat Exchanger Rav Water Inlet Valve / completed per design. | : Procedure Description-DCR 743-33 -Replacement of. Component Cooling Heat Exchanger Rav Water Inlet Valve / completed per design. | ||
EEAR FC-79-7 Seismic Supports for Reactor Missle' Shields / | EEAR FC-79-7 Seismic Supports for Reactor Missle' Shields / | ||
-completed as designed. | -completed as designed. | ||
DCR 76-30 Containment Decon and Cleanup / completed as designed. | DCR 76-30 Containment Decon and Cleanup / completed as designed. | ||
EEAR FC-79-108 Diaphram Modification (WD-9h5 and WD-9h6)/ | EEAR FC-79-108 Diaphram Modification (WD-9h5 and WD-9h6)/ | ||
completed as-designed. | completed as-designed. | ||
E. RESULTS OF LEAK RATE TESTS | E. RESULTS OF LEAK RATE TESTS | ||
'There were no leak rate tests performed during August except ST-CONT-2 by operators on PAL door. | 'There were no leak rate tests performed during August except ST-CONT-2 by operators on PAL door. | ||
F. CHANGES IN PLANT OPERATING STAFF Miss Elizabeth Goebel started with H.P. group 8-18-80, f-G. TRAINING Training for August included the following: | F. CHANGES IN PLANT OPERATING STAFF Miss Elizabeth Goebel started with H.P. group 8-18-80, f-G. TRAINING Training for August included the following: | ||
- EDO Training for plant supervisors. | - EDO Training for plant supervisors. | ||
- System Training for operations.on HVAC, Halon and Fire Detection. ; | - System Training for operations.on HVAC, Halon and Fire Detection. ; | ||
Line 456: | Line 290: | ||
.- Driver training ~for plant personnel. | .- Driver training ~for plant personnel. | ||
'- Emergency sampling. | '- Emergency sampling. | ||
- OIE notices and bulletin review. | - OIE notices and bulletin review. | ||
- Cycle 6 Tech. Spec.'for operations. | - Cycle 6 Tech. Spec.'for operations. | ||
Line 462: | Line 295: | ||
: Safety. meeting for operations,' maintenance and | : Safety. meeting for operations,' maintenance and | ||
.teehnicali groups. | .teehnicali groups. | ||
; -I | ; -I t | ||
t | |||
~ | ~ | ||
E n | E n | ||
n. | n. | ||
r- . | r- . | ||
q_ | |||
* s | |||
s | |||
- < ?hh ' '? * | - < ?hh ' '? * | ||
... - . .e. , , | ... - . .e. , , | ||
?Monthli. Operations.Repdrt Augast 19801 PagelFour | ?Monthli. Operations.Repdrt Augast 19801 PagelFour | ||
.H. - CHANGES, TESTS AND EXPERIMENTS REQUIRING. NUCLEAR REGULATORY-. | .H. - CHANGES, TESTS AND EXPERIMENTS REQUIRING. NUCLEAR REGULATORY-. | ||
COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59.. | COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59.. | ||
Chan6ei; To Facility OperatingL License DPR-40s | Chan6ei; To Facility OperatingL License DPR-40s | ||
.. Amendment No. 50,~ dated August 15,'1980.. . This amendment. | .. Amendment No. 50,~ dated August 15,'1980.. . This amendment. | ||
changed License Co'ndition 3.A'.' and.the Technical Speci-fications to authorize operation-at 1500.MWt. | changed License Co'ndition 3.A'.' and.the Technical Speci-fications to authorize operation-at 1500.MWt. | ||
Amendment No.,51,: dated August 28,.1980. This amendment-deleted certain' environmental monitoring and reporting | Amendment No.,51,: dated August 28,.1980. This amendment-deleted certain' environmental monitoring and reporting | ||
: requirements and increased the maximum and. differential condenser cooling vater discharge temperature limits. | : requirements and increased the maximum and. differential condenser cooling vater discharge temperature limits. | ||
Approved By h. tb- | Approved By h. tb- | ||
' Manager-Foft Calhoun Station- | ' Manager-Foft Calhoun Station-h | ||
h | |||
+ . | + . | ||
, 1 4 | |||
, 1 | |||
4 | |||
. i | . i | ||
~- | ~- | ||
- -.. . . , - ;. - .. | - -.. . . , - ;. - .. | ||
- . ~ - ~ . . . . . . - - | - . ~ - ~ . . . . . . - - | ||
7-p; 'i _ | 7-p; 'i _ | ||
y | y 0 - * ; , '. , . | ||
0 - * ; , '. , . | |||
Monthly. Operations , Report .- | Monthly. Operations , Report .- | ||
~ August,1980. | ~ August,1980. | ||
Line 527: | Line 330: | ||
M- 0. # Oate Description- Corrective Acticn | M- 0. # Oate Description- Corrective Acticn | ||
.6h72 T-16-80: .HCV-1108A vill not shut. Replaced solenoid valve 6h90 7-18-80: CH-13 leak. Replaced valve CH-258. | .6h72 T-16-80: .HCV-1108A vill not shut. Replaced solenoid valve 6h90 7-18-80: CH-13 leak. Replaced valve CH-258. | ||
'6568 ~ 7-21-80 RMO-55 leak.. Tightened intake and- discharge | '6568 ~ 7-21-80 RMO-55 leak.. Tightened intake and- discharge | ||
* flanges. | * flanges. | ||
6832 8-20-80 D-2 Fuel'oi1Ltransfer pumps vill Changed out 0-ring in foot valve. | 6832 8-20-80 D-2 Fuel'oi1Ltransfer pumps vill Changed out 0-ring in foot valve. | ||
Line 535: | Line 338: | ||
I-L I | I-L I | ||
l r | l r | ||
I L | I L | ||
L | L l' | ||
l' | |||
I fi | I fi | ||
: p. . | : p. . | ||
. .:}} | . .:}} |
Revision as of 13:47, 31 January 2020
ML19338D496 | |
Person / Time | |
---|---|
Site: | Fort Calhoun ![]() |
Issue date: | 09/08/1980 |
From: | Hickle B OMAHA PUBLIC POWER DISTRICT |
To: | |
Shared Package | |
ML19338D495 | List: |
References | |
NUDOCS 8009230351 | |
Download: ML19338D496 (9) | |
Text
g _ ,
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_q j..i_" ,
c,
- , . 7 AVERAGE DAILY UNIT POWER LEVEL
. DOCKET NO. 50-285
. 3.iT Fort Calhoun #1 DATE September-8,~1980 CONSPI.ETED BY ~B.
J. Hickle TELEPIIONE _(402)536-4413 MONE August, 1980 ,
' DAY AVERAGE DAILY POWER LEVEL DAY. AVER AGE DAILY POWER LEVEL t- . (MWe-Net) (MWe-Net) 434 37 435 2 433 is 435 3 433 39 432 4 434 20 432 3 434 21 431 6 434 22 431 7A. 433 23 434
- s. 431- 24 435 9 431 25 435 to '432 26 433
.ti 433 27 _
434 L12. 433~ 28 .
437 13 '433 29 436-14- 434- 30 435 i'
-- 15 ; 434 3 435 a
\
16 '434
. INS 1 RUCTIONS O, this format, list the aserage daily unit power level in MWe Net for each day in the reporting nonth. Compute io
. the nearest whole megawatt.
17 7 )
.8009230'351 I ,-.s b
g
g , ; _
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m y < -c..
x' 4
1 /
OPERATING DATA REPORT
- DOCKET NO; 50-285- ~
' DATE Septemoer 8,' 1980 '
COMPLETED BY- B. J. Hickle .
- TELEPilONE (402)53T-4413
> OPERITING STATU}
FortiCalhoun #1 Notes I. Unit Name:
- 2. Reporting Period:. -August, 1980-2 3. Licensed Thermal Power (MWt):
1420
- 4. Namepu.. ; .ing (Gross MWe):- 502-
- 5. Design Electrical Rating (Net MWe):. 457
- 6. Maximum Dependable Capacity (Gross MWe)': 401
'457 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 LevelTo Which Restricted,1f An Net' MWe): N/A
- 10. Reasons For Restrictions.lf Any:
2.
This Month Yr. to-Date Cumulative -
- 11. Ilours in Reporting Period .744.0 5,855.0 60,792.0
- 12. Number Of flours Reactor Was Crit' cal 744'.0 2,449.1-- 46,850.7
- 13. Reactor Reserve Shutdown flours 0.0 0.0 -
1,30925
- 14. Ilours Generator On-Line 744.0 2.387.3- 45;838.4
- 15. Unit Resene Shutdown Hours .- 0.0 0.0- 0.0-
- 16. Gross Thermal Energy Generated (MWH) 1,049,152.6 3,166,746.3: 56,401,725.6- .
- 17. Gross Electrical Energy Generated (MWH) 339.426.0 1.027,932.0 _18,688,161.6 18.- Net Electrical Energy Generated (MWH) 322,571.2 974,199.0 17,661,718.8 .
- 19. . Unit Senice Factor 100.0- 40.8 75.4-20." Unit A'vailability Factor ; 100.0 40.8- : 75.4 .
. 21. Unit Capacity Factor (Using MDC Net) . - 94.9__ 36.4 64.0- g 22.' Unit Capacity Factor (Using DER N'et) . 94.9- 36.4 63.6 23.' Unit Forced Outage Rate 0.0 0.4 -
4.3
- 24. Shutdowns Schedu?ed Over Next 6 Months (Type. Date,and Duration of Eacht
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? 25. If Shut'Down At End Of Report Period. Estimated Da' te of Startup:
k 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY . ->
INITIAL ELECTRICITY
- ~, COMMERCI L OPERATION -
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f Refuclingilnihr.etition =
- Fort ^Calhoun?--Unit No. 1 .
- Reportifor1thenonth' ending August 31,l1980 .- .
1.J Scheduled <date for nes:t' refueling. shutdown. :' September-15,-1981
- 2. i Scheduled date for restart follwing refueling. November 15, 1981
- 3. , 'Will; refuelingfor resumption of operation thereafter
- require altechnical specification change or other No
-licenseJanendment?
, ' a.: ; If' answer is yes, what, ~in general,;will
.these be?'
- b. 'If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unreviewed safety. questions NO are associated withLthe core reload.
- c. If no such review has.taken place, when is September 1,'1981 it scheduled?
- 4. Scheduled-date(s)" for submitting proposed licensing :
action ~and support information.
~5. Important licensing considerations associated with refueling, e.g. , inew or different fuel design or supplier, unroviewed design or performance analysis nethods, significant changes in fuel design, new
- operating procedures. .
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133 assemblics
- 6. We ntmber of fuel assenblies: a) in the core
~
b) in the spent-fuel pool 197 c): spent' fuel pool' "
. rstorage capacity 483 d)-planned spent fuel' pool * "
' storage capacity 483 7.' l'Ihe projected ~datefof: the. last refueling that can be discharged'to ;thejspentifuel pool'asstnting the present 1985 Llicensed capacityn EMM . September 5,E1980
~ '
< <? Prepared'by .
Datc~
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OMAHA- PUBLIC POWER DISTRICT .
Fort:Calhoun. Station Unit'No.'1
' August 1980 _.
J Monthly Operations Report I. OPERATIONS'SUMARY Fort Calhoun Station' received a license amendment during the month-Lof August which: allowed an. increase 1:s power level'to 1500 MWth. The operations department participated in the review of the operational-readiness of Fort-Calhoun~ Station to increase power-level. Plant
. specific: training was given the Fort Calhoun staff on the expected
. s,r.. tem parameter: and procedure changes which vere required to implement
'tbe-increased power level.
Normal surveillance tests and operational tests were completed with no abnormal results reported.
The unit operated at a nominal 1h20 MWth during the month of August.
Normal six shift training continued during August.
A. . PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 80-012: During performance of ST-RPS-3, F.2, it was discovered that Trip Unit #3 (Reactor Coolant Flow) trip setpoints had drifted,out of specifi-cation in the nonconservative direction. Main-tenance: order #6405 was written to investigate the drift. The R.P.S. was immediately placed in a two-out-of-three logic to trip mode.
Technical Specification 1 3(2) applies.
LER-80-013 During normal power' operation it-vas noted that ,
-Channel AJDC. sequencer SI-1 had a de-energized "on-auto" light associated with AC-3A, or the i safeguards equipment supplied 1from Bus 133B.
.The'AC sequencer.for. channel A relatra safeguards
. equipment remained-operable throughout the event as were the. channel B AC and'DC sequencers. .The safeguards loads from all h80 volt equipment, except 1B3B associated equirment (which is AC-3A
.only) remained operable from the DC channel A sequencer SI-1.
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LMonthly< Operations (Report-IAugust.1980' i
iPage Two
- -
I ' A .'
PERFORMANCE CHARACTERISTICS (Continued)
-LER Number ~ . _ Deficiency .
'LER 80-01h : Transformer -(Th) of DG-r failed. This transformer fed power ;to .the diesel's oil' immersion heater as v ell as.; alarm circuitry; corresponding to _the following items: lLov. lube oil; pressure, lov lube oil level,2and.High orJLov lube oil' temperature.
During the time of the transformer. (Th) failure,-
DG-2 as(vell , the 161KV 'and: 3h5KV systems were available:and. operable and would have been more than capable of mitigating the _ circumstances of '
an accident should the need arise. :In addition, DG-1 wasEconsidered~ inoperable only during'the-time-that the transformer was being changed out,
. i.e. only while DG-1 was in " local maintenance."
LER 80-015 During routine' inspection, it was noted that trip unit setpoints on "C" channel, trip unit.hl(Steam
~
Generator Level) had become positive rather than negative. Maintenance' order 6430 was written to investigate and repair the problem. The RPS was immediately placed in a'two-out-of-three logic to trip mode. ' Technical Specification 1.3(5)' applies.
B. CHANGES IN OPERATING METh0DS-None C.- RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None
'D. : CHANGES', TESTS AND _ EXPERIMENTS CARRIED OUT WITHOUT COLMISSION
. APPROVAL i
Procedure Description SP-RPS-5 Excore Detector Symmetric Offset recalibration/
no adjustment required.
'SP- FAUD-l ' Fuel Assembly Uplift Condition Detection /all results normal.
SPAPRC-3' Reactivity Computer and Beactor Physics Content adjustment /results are normal.
- EEAR(FC-79-166- LCV-2 Replacement / completed per procedure.
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~ Monthly Operations Report August 1980.
Page Three D. LCHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL'(Continued)
- Procedure Description-DCR 743-33 -Replacement of. Component Cooling Heat Exchanger Rav Water Inlet Valve / completed per design.
EEAR FC-79-7 Seismic Supports for Reactor Missle' Shields /
-completed as designed.
DCR 76-30 Containment Decon and Cleanup / completed as designed.
EEAR FC-79-108 Diaphram Modification (WD-9h5 and WD-9h6)/
completed as-designed.
E. RESULTS OF LEAK RATE TESTS
'There were no leak rate tests performed during August except ST-CONT-2 by operators on PAL door.
F. CHANGES IN PLANT OPERATING STAFF Miss Elizabeth Goebel started with H.P. group 8-18-80, f-G. TRAINING Training for August included the following:
- EDO Training for plant supervisors.
- System Training for operations.on HVAC, Halon and Fire Detection. ;
- Fire brigade training for plant personnel.
- Radioactive material handling for CARP personnel. '
- Stretch power for all staff and operations personnel. I
.- Driver training ~for plant personnel.
'- Emergency sampling.
- OIE notices and bulletin review.
- Cycle 6 Tech. Spec.'for operations.
~
- Safety. meeting for operations,' maintenance and
.teehnicali groups.
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?Monthli. Operations.Repdrt Augast 19801 PagelFour
.H. - CHANGES, TESTS AND EXPERIMENTS REQUIRING. NUCLEAR REGULATORY-.
COMMISSION AUTHORIZATION PURSUANT TO 10CFR50 59..
Chan6ei; To Facility OperatingL License DPR-40s
.. Amendment No. 50,~ dated August 15,'1980.. . This amendment.
changed License Co'ndition 3.A'.' and.the Technical Speci-fications to authorize operation-at 1500.MWt.
Amendment No.,51,: dated August 28,.1980. This amendment-deleted certain' environmental monitoring and reporting
- requirements and increased the maximum and. differential condenser cooling vater discharge temperature limits.
Approved By h. tb-
' Manager-Foft Calhoun Station-h
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Monthly. Operations , Report .-
~ August,1980.
~ Page' = Five
'II. MAINTENANCE (Significant Safety Related)
M- 0. # Oate Description- Corrective Acticn
.6h72 T-16-80: .HCV-1108A vill not shut. Replaced solenoid valve 6h90 7-18-80: CH-13 leak. Replaced valve CH-258.
'6568 ~ 7-21-80 RMO-55 leak.. Tightened intake and- discharge
6832 8-20-80 D-2 Fuel'oi1Ltransfer pumps vill Changed out 0-ring in foot valve.
-not pick up suction.
I665h 8-7-80 RM-055 flange leak. Install new gasket.
6579 8 h-80 CH-1B has internal leak. Replaced gaskets and 3 discharge-valves.
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