ML19242D256: Difference between revisions
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OPERATING DATA REPORT DOCKETNO. 50-285 DATE Augus t 9, 1979 COSIPLETED BY b. d. til ck le TELEPilONE l*Udl 536-4413 OPERATING STATUS | OPERATING DATA REPORT DOCKETNO. 50-285 DATE Augus t 9, 1979 COSIPLETED BY b. d. til ck le TELEPilONE l*Udl 536-4413 OPERATING STATUS | ||
Line 30: | Line 29: | ||
: 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons: | : 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons: | ||
N/A | N/A | ||
: 9. Power Level To which Restricted. If Any (Net SIWE): O ~ | : 9. Power Level To which Restricted. If Any (Net SIWE): O ~ | ||
: 10. Reasons For Restrictions,If Any: N/A | : 10. Reasons For Restrictions,If Any: N/A This $1onth Yr.-to-Date Cumulative | ||
This $1onth Yr.-to-Date Cumulative | |||
: 11. Ilours In Reporting Perioc' ' | : 11. Ilours In Reporting Perioc' ' | ||
* b | * b | ||
Line 52: | Line 48: | ||
January 1,1980 - Refueling Outage - Two-month Duration | January 1,1980 - Refueling Outage - Two-month Duration | ||
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A | : 25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A | ||
: 26. Units in Test Status t Prior to Commercial Operation): Forecast Achiesed | : 26. Units in Test Status t Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY . | ||
INITIA L ELECTRICITY CO\tNIERCI A L OPER ATION 7 , | |||
INITIA L CRITICA LITY . | |||
INITIA L ELECTRICITY CO\tNIERCI A L OPER ATION | |||
7 , | |||
J L '' | J L '' | ||
(9/77 ) | (9/77 ) | ||
7908140 7 g@>fp | 7908140 7 g@>fp | ||
AVERAGE DAILY UNIT POWER LEVEL | AVERAGE DAILY UNIT POWER LEVEL | ||
~ 50-285 DOCKET NO. | ~ 50-285 DOCKET NO. | ||
UNIT Ft. Calhoun #1 DATT. | UNIT Ft. Calhoun #1 DATT. | ||
July 9, 1979 COMPLETED BY B. J. Hickle TELEPilONE (402) 536-4413 MONTil July, 1979 DAY AVERAGE I PO ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1 439.5 437.3 37 2 439.1 ,g 438.7 3 | July 9, 1979 COMPLETED BY B. J. Hickle TELEPilONE (402) 536-4413 MONTil July, 1979 DAY AVERAGE I PO ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1 439.5 437.3 37 2 439.1 ,g 438.7 3 | ||
437.2 438.6 436.0 438.4 4 ,o | 437.2 438.6 436.0 438.4 4 ,o 438.7 438.5 5 21 441.0 438.5 6 | ||
*0 438.0 7 23 8 | *0 438.0 7 23 8 | ||
2., 437.5 9 | |||
443.9 436.4 25 10 441.6 | 443.9 436.4 25 10 441.6 | ||
'6 436.8 11 438.8 ,7 434.6 12 437.2 435.9 | '6 436.8 11 438.8 ,7 434.6 12 437.2 435.9 | ||
Line 82: | Line 66: | ||
437.2 13 437.3 437.4 14 3g 15 436.8 438.3 3 | 437.2 13 437.3 437.4 14 3g 15 436.8 438.3 3 | ||
I6 437.1 INS'IRUCTIONS On this format, list the average dady unit power levelin MWe Net for each day in the reportine inonth. C.unpute tii the nearest whole megawatt. | I6 437.1 INS'IRUCTIONS On this format, list the average dady unit power levelin MWe Net for each day in the reportine inonth. C.unpute tii the nearest whole megawatt. | ||
(9/77) | (9/77) | ||
, [, ' | , [, ' | ||
* JLJ e | * JLJ e | ||
Line 94: | Line 74: | ||
v- ' - | v- ' - | ||
e | e | ||
<~ 2 m, . n. | <~ 2 m, . n. | ||
m .- | m .- | ||
mn | mn | ||
'= | '= | ||
E cE | E cE | ||
= c. | = c. | ||
Line 110: | Line 87: | ||
=Om OQ=>x Type} | =Om OQ=>x Type} | ||
in g d o:6 :ic_d:x.e ico h.c | in g d o:6 :ic_d:x.e ico h.c | ||
= | = | ||
u e n - = c. a. - . -- c. o- | u e n - = c. a. - . -- c. o- | ||
- u =u =.nc aa a - | - u =u =.nc aa a - | ||
:.:E: 3 g Duration nen::n | :.:E: 3 g Duration nen::n | ||
-=- - | -=- - | ||
Ea om 1 S. E W n- (flours) | Ea om 1 S. E W n- (flours) | ||
E. x eu an e u. .=-n | E. x eu an e u. .=-n | ||
=n = | =n = | ||
4 5 "* . dE 9 s-9. E"m Reason 2 | 4 5 "* . dE 9 s-9. E"m Reason 2 | ||
,-~ CE r. | ,-~ CE r. | ||
u n m-3- =, e. Method el. | u n m-3- =, e. Method el. | ||
~ ^ S C m ShutunE 2 x Down Reactor 3 q E m | ~ ^ S C m ShutunE 2 x Down Reactor 3 q E m | ||
= x - | = x - | ||
C E m | C E m x m ~4 z a m -- | ||
x m ~4 | |||
z a m -- | |||
r- O ~ | r- O ~ | ||
m<R W O 5gn H t | m<R W O 5gn H t | ||
-Ea w 2 4 3 2 | -Ea w 2 4 3 2 | ||
M | M d 2 w . o m | ||
d 2 w . o m | |||
uwu-r c O A3&9g System c x m | uwu-r c O A3&9g System c x m | ||
EcC09 Code 4 N" :D g =; cC = s eC., | EcC09 Code 4 N" :D g =; cC = s eC., | ||
Line 151: | Line 116: | ||
-< x | -< x | ||
?O | ?O | ||
< c Mm | < c Mm C | ||
2m- r n s>N F r- 2 Qqm 5 - = | |||
* m -. | * m -. | ||
wp HM | wp HM E | ||
E | |||
~~* EE ~ | ~~* EE ~ | ||
"C m | "C m | ||
Line 186: | Line 147: | ||
- v -= - | - v -= - | ||
x L c 3' M O' O= 0 O ^ | x L c 3' M O' O= 0 O ^ | ||
8 7 | 8 7 | ||
- n C | - n C | ||
a 4 tb 4 W % 'ik | a 4 tb 4 W % 'ik W WW ( | ||
W WW ( | |||
4 % | 4 % | ||
- - -- . ~ ~ _ . . | - - -- . ~ ~ _ . . | ||
e Refueling Infomation Fort Calhoun - Unit No. 1 | |||
e | |||
~ | ~ | ||
a Report for the nenth ending . July 31,1979 , | a Report for the nenth ending . July 31,1979 , | ||
Line 206: | Line 159: | ||
: 3. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? | : 3. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? | ||
: a. If answr is yes, what, in general, will these be? | : a. If answr is yes, what, in general, will these be? | ||
Stretching power to 1500 PWth is planned ir conjunction with .the change in fuel supplier to Exxon. | Stretching power to 1500 PWth is planned ir conjunction with .the change in fuel supplier to Exxon. | ||
: b. If answer is no, has the relcad fuel design and core configuration been reviewed by your Plant Safety Review Conr.uttee to deter-mine whether any unreviewed safety questions are associated with the core reload, | : b. If answer is no, has the relcad fuel design and core configuration been reviewed by your Plant Safety Review Conr.uttee to deter-mine whether any unreviewed safety questions are associated with the core reload, | ||
: c. If no such review has taken place, when is | : c. If no such review has taken place, when is it scheduled? | ||
it scheduled? | |||
Stretch Pov er Aoplicatic- | Stretch Pov er Aoplicatic- | ||
: 4. Scheduled date(s) for sub:nitting proposed licensing . Site Related Information , | : 4. Scheduled date(s) for sub:nitting proposed licensing . Site Related Information , | ||
Line 220: | Line 169: | ||
First use of Exxon fuel in Fort Calhoun. ' | First use of Exxon fuel in Fort Calhoun. ' | ||
Stretching power from 1420 MWth to 1500 MWth. | Stretching power from 1420 MWth to 1500 MWth. | ||
: 6. The nc er of fuel assentlies: a) in the core 133 assemblies b) in the s p t fuel pcol 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool " | |||
: 6. The nc er of fuel assentlies: a) in the core 133 assemblies | |||
b) in the s p t fuel pcol 157 | |||
c) spent fuel pool | |||
storage capacity 483 d) planned spent fuel pool " | |||
storage capacity 483 | storage capacity 483 | ||
: 7. W.e projected date af the last refueling that can he discharged to the spt fuel pool assu: ring the present 1985 licensed caoacity. | : 7. W.e projected date af the last refueling that can he discharged to the spt fuel pool assu: ring the present 1985 licensed caoacity. | ||
Line 234: | Line 175: | ||
~ | ~ | ||
tate August 1, 1979 | tate August 1, 1979 | ||
~,4 m | |||
J L. i | |||
~,4 | |||
____ ~ _ __ .. | ____ ~ _ __ .. | ||
OMAHA FUELIC PO'iER DISTRICT Fort Calhoun Station Unit No. 1 July 1979 | OMAHA FUELIC PO'iER DISTRICT Fort Calhoun Station Unit No. 1 July 1979 | ||
!! nthly Operations Report I. OPERATIONS | !! nthly Operations Report I. OPERATIONS | ||
Line 260: | Line 196: | ||
- .m- r.n.Je. . m,14 6* 6v A.,0 NOHE C. RESULTS OF SURVIILIX;CE TESTS AliD I:ISPECTIO:;S The following is a surveillance test where an unusual result occurred: | - .m- r.n.Je. . m,14 6* 6v A.,0 NOHE C. RESULTS OF SURVIILIX;CE TESTS AliD I:ISPECTIO:;S The following is a surveillance test where an unusual result occurred: | ||
Surveillance Test '!c . Descrirtion ST-?M-3 20: conpleted within specifie:1 period of time. | Surveillance Test '!c . Descrirtion ST-?M-3 20: conpleted within specifie:1 period of time. | ||
b d | b d | ||
. ~ | . ~ | ||
Monthly Operations Report Page Two July 1979 D. CHA'IGES, TESTS AND EXPERIME';TS CARRIED OUT WITHOUT C0:01ISSION APPROVAL Prneedure Descrintion ST-RPS-5 Execre Detector Sy==etric Offset Calibraticn: | Monthly Operations Report Page Two July 1979 D. CHA'IGES, TESTS AND EXPERIME';TS CARRIED OUT WITHOUT C0:01ISSION APPROVAL Prneedure Descrintion ST-RPS-5 Execre Detector Sy==etric Offset Calibraticn: | ||
Line 285: | Line 219: | ||
#. t L. I a | #. t L. I a | ||
Monthly Operations Report Fage Three July 1979 D. Continued Procedure Descrintion DCR 76A-13 Modificaticn of Feedvater Heater Pipe Supports / | Monthly Operations Report Fage Three July 1979 D. Continued Procedure Descrintion DCR 76A-13 Modificaticn of Feedvater Heater Pipe Supports / | ||
cc=pleted as designed. | cc=pleted as designed. | ||
Line 299: | Line 231: | ||
- m.. | - m.. | ||
_.. r.r . O,r =- wi .s a oia r | _.. r.r . O,r =- wi .s a oia r | ||
,4 s G s1 ., | ,4 s G s1 ., | ||
c. | c. | ||
2 m. .aA .. -.. .ss s The training at Fort Calhoun Station consisted cf requalification training and hot license training for the operators, Radiation Protection Training, First Aid Training and general system training for the crafts. | 2 m. .aA .. -.. .ss s The training at Fort Calhoun Station consisted cf requalification training and hot license training for the operators, Radiation Protection Training, First Aid Training and general system training for the crafts. | ||
: 3. CHA: IGE 3, TE3TS A!!D EXPERIEITS REQUIRING NUCLEAR REGULATORY CC'SIISCIO:i AL"HORI7ATIO: FURCUA:T TO 10 CFR 50.59 Changes to Operating License DPR k0 Amendment No. h6 dated July 2,1979 The amendment revised the Technical Specificatiens to incorporate surveillance requirecents fcz in-service inspection of stea generator tubes and replaced existing in-service inpsection and testing Technical Specifications with an in-service inspection and terting program that meets the requirements of 10CFR50.55A. | : 3. CHA: IGE 3, TE3TS A!!D EXPERIEITS REQUIRING NUCLEAR REGULATORY CC'SIISCIO:i AL"HORI7ATIO: FURCUA:T TO 10 CFR 50.59 Changes to Operating License DPR k0 Amendment No. h6 dated July 2,1979 The amendment revised the Technical Specificatiens to incorporate surveillance requirecents fcz in-service inspection of stea generator tubes and replaced existing in-service inpsection and testing Technical Specifications with an in-service inspection and terting program that meets the requirements of 10CFR50.55A. | ||
Antroyed b'/ - | Antroyed b'/ - | ||
'hnager-For: Calhoun Station e | |||
'hnager-For: Calhoun Station | i7it 4 .) J U e | ||
Monthly Operations RepoM. | |||
July 1979 Pas ? Four II. MAI::TEUd'CI (Significant Safety Related) | July 1979 Pas ? Four II. MAI::TEUd'CI (Significant Safety Related) | ||
:/. . O. | :/. . O. | ||
Line 323: | Line 247: | ||
=isaing on upper support Cenpleted per M.0. | =isaing on upper support Cenpleted per M.0. | ||
1h25 T-2 5-79 SIS-2TA pipe support nut missing frc= bolt en support SIS-27A Cc=pleted per M.0. | 1h25 T-2 5-79 SIS-2TA pipe support nut missing frc= bolt en support SIS-27A Cc=pleted per M.0. | ||
.. J l | .. J l | ||
.}} | .}} |
Latest revision as of 02:28, 2 February 2020
ML19242D256 | |
Person / Time | |
---|---|
Site: | Fort Calhoun |
Issue date: | 08/09/1979 |
From: | Hickle B OMAHA PUBLIC POWER DISTRICT |
To: | |
Shared Package | |
ML19242D253 | List: |
References | |
NUDOCS 7908140758 | |
Download: ML19242D256 (8) | |
Text
.
~
OPERATING DATA REPORT DOCKETNO. 50-285 DATE Augus t 9, 1979 COSIPLETED BY b. d. til ck le TELEPilONE l*Udl 536-4413 OPERATING STATUS
- 1. 81 nit Name: Fort Calhoun Station Unit No. 1 Notes
- 2. Reporting Period: July, 1979
- 3. Licensed Thermal Power (SIWt): 1420
- 4. Namephte Rating (Gross 5!We): 502
- 5. Design Electrical Ratini;(Net SIWE): 457
- 6. Staximum Dependable Capacity (Gross SlWe): 481
- 7. Staximum Dependable Capacity (Net SIWE): 457
- 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To which Restricted. If Any (Net SIWE): O ~
- 10. Reasons For Restrictions,If Any: N/A This $1onth Yr.-to-Date Cumulative
- 11. Ilours In Reporting Perioc' '
- b
- 12. humber Of flours Reactc,r % Critical 744 5,065.4 41,'030.4
- 13. Reactor Reserve Shutdown riours 0 0 1136.0
- 14. Ilours Generator On Line 744 5,050.6 40,116.7 _
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (51WH) 1,045,094.0 6,974,567.3 _ 48,622,990.6 .
- 17. Gross Electrical Energy Generated (5tWH) 343,142.0 2,345,221.9 15,149,483.6
- 18. Net Electrical Energy Generated (5thil) 326,235.1 2,230,894.2 15,252,299.9
- 19. Unit Sersice Factnr 100.0 99.3 78.3
- 20. Unit Assilability Factor 100.0 99.3 78.3
- 21. Unit Capacity Factor (Using .\lDC Net) . 96.0 65.7
- 22. Unit Capacity Factor (Using DER Net) 95.9 96.0 65.1
- 23. Unit Forced Outage Rate 0.0 0. 7 4.5
- 24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration of Eachi:
January 1,1980 - Refueling Outage - Two-month Duration
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A
- 26. Units in Test Status t Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY .
INITIA L ELECTRICITY CO\tNIERCI A L OPER ATION 7 ,
J L
(9/77 )
7908140 7 g@>fp
AVERAGE DAILY UNIT POWER LEVEL
~ 50-285 DOCKET NO.
UNIT Ft. Calhoun #1 DATT.
July 9, 1979 COMPLETED BY B. J. Hickle TELEPilONE (402) 536-4413 MONTil July, 1979 DAY AVERAGE I PO ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1 439.5 437.3 37 2 439.1 ,g 438.7 3
437.2 438.6 436.0 438.4 4 ,o 438.7 438.5 5 21 441.0 438.5 6
- 0 438.0 7 23 8
2., 437.5 9
443.9 436.4 25 10 441.6
'6 436.8 11 438.8 ,7 434.6 12 437.2 435.9
,3 436.8 ,
437.2 13 437.3 437.4 14 3g 15 436.8 438.3 3
I6 437.1 INS'IRUCTIONS On this format, list the average dady unit power levelin MWe Net for each day in the reportine inonth. C.unpute tii the nearest whole megawatt.
(9/77)
, [, '
- JLJ e
')
. ~,2 C, ,y* -
v- ' -
e
<~ 2 m, . n.
m .-
mn
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ID w t
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=Om OQ=>x Type}
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=
u e n - = c. a. - . -- c. o-
- u =u =.nc aa a -
- .:E: 3 g Duration nen::n
-=- -
Ea om 1 S. E W n- (flours)
E. x eu an e u. .=-n
n
4 5 "* . dE 9 s-9. E"m Reason 2
,-~ CE r.
u n m-3- =, e. Method el.
~ ^ S C m ShutunE 2 x Down Reactor 3 q E m
= x -
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r- O ~
m<R W O 5gn H t
-Ea w 2 4 3 2
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uwu-r c O A3&9g System c x m
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- g m
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'^n
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8 7
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a 4 tb 4 W % 'ik W WW (
4 %
- - -- . ~ ~ _ . .
e Refueling Infomation Fort Calhoun - Unit No. 1
~
a Report for the nenth ending . July 31,1979 ,
- 1. Scheduled date for next refueling shutdown. January 1,1980 Scheduled date for restart following refueling. March 1,1980 2.
- 3. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?
- a. If answr is yes, what, in general, will these be?
Stretching power to 1500 PWth is planned ir conjunction with .the change in fuel supplier to Exxon.
- b. If answer is no, has the relcad fuel design and core configuration been reviewed by your Plant Safety Review Conr.uttee 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 Pov er Aoplicatic-
- 4. Scheduled date(s) for sub:nitting proposed licensing . Site Related Information ,
action and support infccation. Jul v . 1979 - Submitted Non-Core Related Informa-
- 5. Ir. ortant licensir.g considerations associated with tion , October,1979 refueling, e.g. , new or different fuel design er Core Related Analysis and supplier, unreviewed design or perfor.ance analysis -
Tech. Spec. Changes, methods, sicnificant changes in fuel design, new November, 1979 cperating procedures.
First use of Exxon fuel in Fort Calhoun. '
Stretching power from 1420 MWth to 1500 MWth.
- 6. The nc er of fuel assentlies: a) in the core 133 assemblies b) in the s p t fuel pcol 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool "
storage capacity 483
- 7. W.e projected date af the last refueling that can he discharged to the spt fuel pool assu: ring the present 1985 licensed caoacity.
Prepared by k
~
tate August 1, 1979
~,4 m
J L. i
____ ~ _ __ ..
OMAHA FUELIC PO'iER DISTRICT Fort Calhoun Station Unit No. 1 July 1979
!! nthly Operations Report I. OPERATIONS
SUMMARY
Fort Calhoun operated near a nc=inal 100T, power during the month of July. '"he fire protection projects continued en site.
Post Three Mile Island training continued as the shifts rotated through the training week.
A =utual fire drill was held with the Blair Fire Departnent. "'his drill de=cnstrated the ability of the Blair Fire Department pu=p truck to take suction from the Missouri River and pressurice the station fire header. This capability provides a defense in depth for providing fire suppression water at Fcrt Calhou . Statien.
The annual nu,: lear emergency drill was held during July. The oper-ations group at the plant responded to the alert and no significant deficiencies were noted.
- Icr
- al in service, surveillance and operational testing were per-for=ed.
The training cf a hot license candidate grcup continued in pre-paration for the examination in late Auguct.
A. FERFCFy2iCI CHARACTERISTICS LEP. !!unber Deficiency NOME un,-
a.
u un..hJ
. . ~ wr.s 7-4 1 cJ.o rn
- .m- r.n.Je. . m,14 6* 6v A.,0 NOHE C. RESULTS OF SURVIILIX;CE TESTS AliD I:ISPECTIO:;S The following is a surveillance test where an unusual result occurred:
Surveillance Test '!c . Descrirtion ST-?M-3 20: conpleted within specifie:1 period of time.
b d
. ~
Monthly Operations Report Page Two July 1979 D. CHA'IGES, TESTS AND EXPERIME';TS CARRIED OUT WITHOUT C0:01ISSION APPROVAL Prneedure Descrintion ST-RPS-5 Execre Detector Sy==etric Offset Calibraticn:
Parameters within limit:, no recalibration required.
FM-RM-1 Radioactive Source Surveillance of Licensed Sources not at the Fort Calhoun Station.
DCR 79-84 Install audible alarms en peri.a1 = nitor in Security Building.
SP-FAUD-1 Fuel Asse=bly Uplift Condition Detectien/all loops with available instrumentation show greater than 99% assu ance.
M.O. 10699 Install PR's in New Fuel Storage Area RM-25A/
c0=pleted as designed.
SP-CONT-2 Contain=ent Purge Supply and Exhaust Fenetration (M-88 and M-87) ?f pe C Leak Rate Test /c:=pleted per procedure.
SP-DI-2 Water Flant rem -"' "*ng Test /c0=pleted per procedure. Plant Er. gin-ers evaluating results.
SP-FAUD-1 Fuel Asse=bly Uplift Condition Detection /all loops with available instru.=entation show grecter than 995 assurance.
M.O. 933 VA-TlA & 3/cc=pleted as designed M.0. 10200 Additional FR's in Roc = Tl/ccepleted as designed.
EEAR 79-115 Centrol Switch-Ereaker 1A22/Cc=pleted as designed.
M.O. 3625 Additional PR's in Roc = 69/cc=pleted per design.
DCR 77-26 Auxiliary Euilding Fire Protection Systen - Diesel Generator S)rinkler "odification/c =pleted as designed.
SP-RPS-5 Excore Detector Synnetric Off Set Rec nibraticn/
c =pleted per procedure.
DCR 78-53 Fire d1=per =odification/cc=pleted as designed.
DCR TT k5 Fire Protection Water Line Tie-in "cr Zecu-ity 3uilding/ccepleted as designed.
- . t L. I a
Monthly Operations Report Fage Three July 1979 D. Continued Procedure Descrintion DCR 76A-13 Modificaticn of Feedvater Heater Pipe Supports /
cc=pleted as designed.
EEAR 79-22 Security Diesel Battery 3ack/ completed per design.
EEAR T3 h5 Bullet Nose Pressurization / completed per design.
E. RESULTS OF LF.AK RATE TESTS The six month 60 psig leak rate tegt was perfor=ed on the Fer-scnnel Air Lock. 3esults were within the .6 L, li=it.
a
+ - --.--
e.
. u . . 2 r-C .m. a.
r,,
- m..
_.. r.r . O,r =- wi .s a oia r
,4 s G s1 .,
c.
2 m. .aA .. -.. .ss s The training at Fort Calhoun Station consisted cf requalification training and hot license training for the operators, Radiation Protection Training, First Aid Training and general system training for the crafts.
- 3. CHA: IGE 3, TE3TS A!!D EXPERIEITS REQUIRING NUCLEAR REGULATORY CC'SIISCIO:i AL"HORI7ATIO: FURCUA:T TO 10 CFR 50.59 Changes to Operating License DPR k0 Amendment No. h6 dated July 2,1979 The amendment revised the Technical Specificatiens to incorporate surveillance requirecents fcz in-service inspection of stea generator tubes and replaced existing in-service inpsection and testing Technical Specifications with an in-service inspection and terting program that meets the requirements of 10CFR50.55A.
Antroyed b'/ -
'hnager-For: Calhoun Station e
i7it 4 .) J U e
Monthly Operations RepoM.
July 1979 Pas ? Four II. MAI::TEUd'CI (Significant Safety Related)
- /. . O.
- Oate l Description Corrective Action i
i 1202 T-7-79 SIS ko Anchor Bolts Cc=pleted per procedure 1155 T-9-79 Stud Tensioning per Bulletin 79-02 Completed per procedure 133h T 79 RPS-Channel "A" V0PT =eter operating i= properly Cer.pleted per procedure 1421 T-25-79 MSS-10/CCncrete expansion anchor located in south baseplate Cc=pleted per M.O.
1L26 T-2 5-79 SIS-27 Pipe support cotter pin
=isaing on upper support Cenpleted per M.0.
1h25 T-2 5-79 SIS-2TA pipe support nut missing frc= bolt en support SIS-27A Cc=pleted per M.0.
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