ML19331C471: Difference between revisions
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O TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kT.R SEQUOYAH NUCLEAR PLANT MONTHLY fPERATING REPORT JULY 1, 1980 - JULY 31, 1980 DOCKET NUMBER 50-327 i | O TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kT.R SEQUOYAH NUCLEAR PLANT MONTHLY fPERATING REPORT JULY 1, 1980 - JULY 31, 1980 DOCKET NUMBER 50-327 i | ||
LICENSE NLHBER DPR-77 , | LICENSE NLHBER DPR-77 , | ||
J .- | J .- | ||
i I | i I | ||
mh-Submitted by,. D w. Ditkii,g Plan) Superintendent f | mh-Submitted by,. D w. Ditkii,g Plan) Superintendent f | ||
8 008150 //4 AI a.- - . _ . . _ _ _ . - - - . - - _ _ . _ _ _ _ _ | 8 008150 //4 AI a.- - . _ . . _ _ _ . - - - . - - _ _ . _ _ _ _ _ | ||
* a - " | * a - " | ||
e | e | ||
* . l l | * . l l | ||
l TABLE OF CONTENTS Operations Susumary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 3 Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . . 5-6 Plant Maintenance Summary . . .. . . . . . . . . . . . . . . . . . . . . 7 4 | l TABLE OF CONTENTS Operations Susumary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 3 Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . . 5-6 Plant Maintenance Summary . . .. . . . . . . . . . . . . . . . . . . . . 7 4 | ||
Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 8 i | Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 8 i | ||
1 1 | 1 1 | ||
.i J | .i J | ||
l | l | ||
---r -~<vv-e ,nv. v,m--- rr - e, ew- e.- - sr. ,vr-,,--,-m,,w _nr-e,------,,-n-m w e e ,- e - w w r-e w e w-~ -r --,-----~,--remy-r, ---,y,----, -wr -s-w- w+w vm-wm- - - - ~ - g - | ---r -~<vv-e ,nv. v,m--- rr - e, ew- e.- - sr. ,vr-,,--,-m,,w _nr-e,------,,-n-m w e e ,- e - w w r-e w e w-~ -r --,-----~,--remy-r, ---,y,----, -wr -s-w- w+w vm-wm- - - - ~ - g - | ||
O Operations Summary July 1980 The following summary describes the significant operational activities during the reporting perfod. In support of this summary, a chronological log of significant events is included in this report. | |||
O | |||
Operations Summary July 1980 The following summary describes the significant operational activities during the reporting perfod. In support of this summary, a chronological log of significant events is included in this report. | |||
There were thirty-four Licensee Event Reports and one Special Report 80-2 on the positive moderator temperature coefficient. | There were thirty-four Licensee Event Reports and one Special Report 80-2 on the positive moderator temperature coefficient. | ||
On 7-5-80, 0410,- operation began pulling rods for the approach to initial criticality. At 1040 on 7-5-80, the reactor reached initial criticality. | On 7-5-80, 0410,- operation began pulling rods for the approach to initial criticality. At 1040 on 7-5-80, the reactor reached initial criticality. | ||
There were scien reactor scrams during July of which two were manual scrams that occurred during low power physics tests. | There were scien reactor scrams during July of which two were manual scrams that occurred during low power physics tests. | ||
During July, all low power physics tests were completed. | During July, all low power physics tests were completed. | ||
I i | I i | ||
1 | 1 | ||
~ | ~ | ||
.--n - | .--n - | ||
._,,e+ , - . , - . _ - - . , . -,_m-.., .-- - - - - , - - - ,-,..,,e,-r..-e. - - e - , , - - - , w-, - . , , , -,,,--_.w. y m.,--, -,. , , . -,e,, ~ - | ._,,e+ , - . , - . _ - - . , . -,_m-.., .-- - - - - , - - - ,-,..,,e,-r..-e. - - e - , , - - - , w-, - . , , , -,,,--_.w. y m.,--, -,. , , . -,e,, ~ - | ||
Significant Operational Events Date Time Event 7/05/80 0410 Started pulling shutdown Rank A-rode to begin initial criticality. | Significant Operational Events Date Time Event 7/05/80 0410 Started pulling shutdown Rank A-rode to begin initial criticality. | ||
7/05/80 1040 Initial criticality. | 7/05/80 1040 Initial criticality. | ||
| Line 88: | Line 64: | ||
7/23/80 1334 Decreasing reactor power in preparation for going to mode 4, 7/23/80 1914 Reactor trip was due to low steam generator level in #3 steam generator. | 7/23/80 1334 Decreasing reactor power in preparation for going to mode 4, 7/23/80 1914 Reactor trip was due to low steam generator level in #3 steam generator. | ||
7/24/80 1847 Reactor coolant system is in mode 5. | 7/24/80 1847 Reactor coolant system is in mode 5. | ||
2 | 2 | ||
. - ? . . _ _ . | . - ? . . _ _ . | ||
O a AVERAGE DAILY UNIT POWER LEVEL | |||
O | |||
a AVERAGE DAILY UNIT POWER LEVEL | |||
\ | \ | ||
k' - | k' - | ||
| Line 108: | Line 73: | ||
UNIT DATE, 8-5-80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295 | UNIT DATE, 8-5-80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295 | ||
~ | ~ | ||
MONTH July 1980 | MONTH July 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net) (Mwe. Net) 1 0 17 0 2 0 ig o 3 0 g9 0 4 0 20 0 5 0 21 0 6 0 0 22 I 0 0 '.f 7, 23 | ||
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net) (Mwe. Net) 1 0 17 0 2 0 ig o 3 0 g9 0 4 0 20 0 5 0 21 0 6 0 0 22 I 0 0 '.f 7, 23 | |||
* ~ | * ~ | ||
8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 ;g o | 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 ;g o 13 0 0 29 14 0 0 30 m | ||
13 0 0 29 14 0 0 30 m | |||
15 0 3 J ,, _ | 15 0 3 J ,, _ | ||
.;_ . - . | .;_ . - . | ||
| Line 120: | Line 81: | ||
INSTRUCTIONS | INSTRUCTIONS | ||
' " On this format. list the average daily unit power levelin MWe. Net for each day in the reporting inonth. Compute to the neareit whole megawatt. | ' " On this format. list the average daily unit power levelin MWe. Net for each day in the reporting inonth. Compute to the neareit whole megawatt. | ||
(4 /77) | (4 /77) 3 I 1 | ||
3 I 1 | |||
. j , | . j , | ||
f \ - | f \ - | ||
k OPERATING DATA REPORT | k OPERATING DATA REPORT | ||
| Line 154: | Line 98: | ||
_ , _IO. Rnsons For Restrictions. If Any: *L w P wer Phvefee Tooeing | _ , _IO. Rnsons For Restrictions. If Any: *L w P wer Phvefee Tooeing | ||
.s | .s | ||
'V- This afonth Yr..to.Date Cumulative | 'V- This afonth Yr..to.Date Cumulative | ||
-- I1. Hours in Reporting Period 744 3672 3672 | -- I1. Hours in Reporting Period 744 3672 3672 | ||
| Line 173: | Line 114: | ||
: 23. Unit Forced Outage Rate NA - MA . - -- _-WA--- | : 23. Unit Forced Outage Rate NA - MA . - -- _-WA--- | ||
~ | ~ | ||
~ | ~ | ||
: 24. Shutdowns Scheduled Over Nest 6.\1onths (Type. Date, and Duration of Each N '~vC-s i -12'_M "# Y ' A :'-'- | : 24. Shutdowns Scheduled Over Nest 6.\1onths (Type. Date, and Duration of Each N '~vC-s i -12'_M "# Y ' A :'-'- | ||
8-30 9-8-80 Outane to Inse=11 Hyd'ronen Tenitnrn in conrmin nd ~ ~ | 8-30 9-8-80 Outane to Inse=11 Hyd'ronen Tenitnrn in conrmin nd ~ ~ | ||
- -~ | - -~ | ||
: 25. If Shur Down \t End Of Report Period, Estimated Date of Startup:- ,8-$-80" | : 25. If Shur Down \t End Of Report Period, Estimated Date of Startup:- ,8-$-80" | ||
, ] . | , ] . | ||
: 26. Units in Test Status f Prior to Commercial Operation): | : 26. Units in Test Status f Prior to Commercial Operation): | ||
~ | ~ | ||
Forecasr '' Achies ed ' ' ~ ~ ' ~ - ' | Forecasr '' Achies ed ' ' ~ ~ ' ~ - ' | ||
INITIA L CRITICA LITY 7-4-80 7-5-80 | INITIA L CRITICA LITY 7-4-80 7-5-80 | ||
,. INITIAL ELECTRICITY 8-21-80 7-22-80 | ,. INITIAL ELECTRICITY 8-21-80 7-22-80 CO\l\lERCIA L OPER ATION 10-3-80 4 (9/77) | ||
CO\l\lERCIA L OPER ATION 10-3-80 | |||
4 (9/77) | |||
, ,,w w - ~, n- g ~mn - ----- | , ,,w w - ~, n- g ~mn - ----- | ||
V | V | ||
, Pzgs I cf 2 | , Pzgs I cf 2 | ||
'y . | 'y . | ||
. i 1 | |||
. i | |||
UNil'Silull60WNS ANilPOWl:M Hlllik'llONS IH M'l 1:l' NO. 50-327 ,4? | UNil'Silull60WNS ANilPOWl:M Hlllik'llONS IH M'l 1:l' NO. 50-327 ,4? | ||
,i UNil'NAntti hquoyah i l) Nil; R LRn .. .. | ,i UNil'NAntti hquoyah i l) Nil; R LRn .. .. | ||
' ! COMPl.1lli D llY . frank .M._ Walker 't lli Pulfl AIONill 'Tuly 1980 'll 1.l l'IlONii | ' ! COMPl.1lli D llY . frank .M._ Walker 't lli Pulfl AIONill 'Tuly 1980 'll 1.l l'IlONii | ||
: (615).842r0295 . | : (615).842r0295 . | ||
_.. - . - _ .. = .- - - . - - - . | _.. - . - _ .. = .- - - . - - - . | ||
''t. .,. | ''t. .,. | ||
3p .li | |||
* 1 l leeir nc l[[ | * 1 l leeir nc l[[ | ||
'"I, Caliee .% l'oneilivo No. D.ile h, ' y ij i .f [N'h | '"I, Caliee .% l'oneilivo No. D.ile h, ' y ij i .f [N'h | ||
.; 1: vent y,o'j g .. "] | .; 1: vent y,o'j g .. "] | ||
| Line 235: | Line 146: | ||
Repins u m U | Repins u m U | ||
hevent Recurrente d | hevent Recurrente d | ||
7-8-80 S 6.52 B 2 NA ZZ ZZZZZ Low Power Physics Testing 7-8-80 S 1.71 B 2 NA ZZ ZZZZZ Low Power Physics Testing 1 7-12-80 F 10 A 3 NA TA INSTRUY Reactor Tripped Because I.R. High Flua | 7-8-80 S 6.52 B 2 NA ZZ ZZZZZ Low Power Physics Testing 7-8-80 S 1.71 B 2 NA ZZ ZZZZZ Low Power Physics Testing 1 7-12-80 F 10 A 3 NA TA INSTRUY Reactor Tripped Because I.R. High Flua | ||
' ; | ' ; | ||
Trip Exceeded Setpoint. Inst was 1 | Trip Exceeded Setpoint. Inst was 1 | ||
Checked and Found to be OK. | Checked and Found to be OK. | ||
* 2 7-15-80 F 3.72 ,C 3 NA IA INSTRUR Recorders Used in Special Test were | * 2 7-15-80 F 3.72 ,C 3 NA IA INSTRUR Recorders Used in Special Test were Connected Improperly. When Recorder | ||
Connected Improperly. When Recorder | |||
, was Turned on, the Over Temperature AT Tripped the Reactor. | , was Turned on, the Over Temperature AT Tripped the Reactor. | ||
i . | i . | ||
| Line 259: | Line 165: | ||
C' 1 Opciatos haining & I acmc 1:samination , | C' 1 Opciatos haining & I acmc 1:samination , | ||
IN Ailinunst rative 5 G Opcianonal I.nus (l'xplain) 1:sinbis 1 S.nne Source i pt/77) 11 Other (1:s pl.iin) ! | IN Ailinunst rative 5 G Opcianonal I.nus (l'xplain) 1:sinbis 1 S.nne Source i pt/77) 11 Other (1:s pl.iin) ! | ||
I | I | ||
.) ' | .) ' | ||
Pega 2 pf 2 e UNil Silulil0WNS ANI)l' owl:R RI;DUCllONS IMM:KET No, _ 5D:327 # 1-3' UNil' NAMl; Sequoya ilNIE 8-5-fl0 COMI'I.E llill ilY Frank M. Walker Rt.I'Olt l' MON ~lll ..luly 14An ; | |||
Pega 2 pf 2 e | |||
UNil Silulil0WNS ANI)l' owl:R RI;DUCllONS IMM:KET No, _ 5D:327 # 1-3' UNil' NAMl; Sequoya | |||
ilNIE 8-5-fl0 COMI'I.E llill ilY Frank M. Walker Rt.I'Olt l' MON ~lll ..luly 14An ; | |||
.ll.l.l l lloNg (615)_842-0295 , | .ll.l.l l lloNg (615)_842-0295 , | ||
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l 'E | l 'E | ||
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, - ; u | , - ; u i | ||
i | |||
4 7-23-80 F 196.76 G 3 NA IA INSTRUE A low-low Steam Generator Level Tripped Reactor in Process of Shutting Down | 4 7-23-80 F 196.76 G 3 NA IA INSTRUE A low-low Steam Generator Level Tripped Reactor in Process of Shutting Down | ||
* l J | |||
I 2 3 *l l: l on ril l(cason: kjellunt: 1 Ifthllill () . Inst niclloin | |||
* l | |||
J | |||
I 2 3 *l | |||
l: l on ril l(cason: kjellunt: 1 Ifthllill () . Inst niclloin | |||
$; N hvilnleil A l ignipineni l allnic (l'xplain) l M.ninal l~ns l'arp.nalle'n ol'l)ala Il M.iintenance ni l'est 1 M.ninal &s.nn. linsey Slieces lin I.ictmee C 1(cincling .I Antoniasic & s.un, 1%cna itep.n o (1 l'lO 1 ile INilld i; l a leer.nl.n"* 5 It''* 8 81* t l"n l O'l*vi il $P Iilu n lill* l I i e st'esasi. lea 8Hinr. A 18+ rnse ladniludilon ' | $; N hvilnleil A l ignipineni l allnic (l'xplain) l M.ninal l~ns l'arp.nalle'n ol'l)ala Il M.iintenance ni l'est 1 M.ninal &s.nn. linsey Slieces lin I.ictmee C 1(cincling .I Antoniasic & s.un, 1%cna itep.n o (1 l'lO 1 ile INilld i; l a leer.nl.n"* 5 It''* 8 81* t l"n l O'l*vi il $P Iilu n lill* l I i e st'esasi. lea 8Hinr. A 18+ rnse ladniludilon ' | ||
1 A.linsur.lialue 5 | 1 A.linsur.lialue 5 | ||
(. Upci.ilional 1 nos il spl.nn) I sint.it I S.nne Souice p8/1/) 11 Ollies tl splain) | (. Upci.ilional 1 nos il spl.nn) I sint.it I S.nne Souice p8/1/) 11 Ollies tl splain) | ||
* o Plant Maintenance Sungnary Balanced the number four reactor coolant pump. | |||
o | |||
Plant Maintenance Sungnary Balanced the number four reactor coolant pump | |||
7 | 7 | ||
- - - . , - .,, - - - - , . - - - --- - - ~ - - - - * ~ | - - - . , - .,, - - - - , . - - - --- - - ~ - - - - * ~ | ||
y Outage Maintena=ce Summary Inspected pipe hangers on safety related syscens inside and cutside ccatainment in accordance with a conformatica of actica letter free NRC and II bulletin 79-1/.. | |||
y | |||
Outage Maintena=ce Summary Inspected pipe hangers on safety related syscens inside and cutside ccatainment in accordance with a conformatica of actica letter free NRC and II bulletin 79-1/.. | |||
Repisced the steam valve room exhaust fans v-ith larger capacity fans. | Repisced the steam valve room exhaust fans v-ith larger capacity fans. | ||
This was done to ensare that the steam valve room can be kept at 30 tp 120'T. | This was done to ensare that the steam valve room can be kept at 30 tp 120'T. | ||
4 l | 4 l | ||
s _ | s _ | ||
B | B | ||
~e.e a rw-,--,a,,-- - -- | ~e.e a rw-,--,a,,-- - -- | ||
: w. -p ,- .,n - - <,a - ~ ,---y, -m ,e- c.p - g -.-- -p-n-- , , | : w. -p ,- .,n - - <,a - ~ ,---y, -m ,e- c.p - g -.-- -p-n-- , , | ||
: p. -ge- g. g p-,- -p-- e-}} | : p. -ge- g. g p-,- -p-- e-}} | ||
Revision as of 16:37, 31 January 2020
| ML19331C471 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/05/1980 |
| From: | Ballentine J, Walker F TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19331C466 | List: |
| References | |
| NUDOCS 8008180444 | |
| Download: ML19331C471 (10) | |
Text
{{#Wiki_filter:. O TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0kT.R SEQUOYAH NUCLEAR PLANT MONTHLY fPERATING REPORT JULY 1, 1980 - JULY 31, 1980 DOCKET NUMBER 50-327 i LICENSE NLHBER DPR-77 , J .- i I mh-Submitted by,. D w. Ditkii,g Plan) Superintendent f 8 008150 //4 AI a.- - . _ . . _ _ _ . - - - . - - _ _ . _ _ _ _ _
- a - "
e
* . l l
l TABLE OF CONTENTS Operations Susumary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 2 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 3 Operating Data Report . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . . . . . . . 5-6 Plant Maintenance Summary . . .. . . . . . . . . . . . . . . . . . . . . 7 4 Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 8 i 1 1 .i J l
---r -~<vv-e ,nv. v,m--- rr - e, ew- e.- - sr. ,vr-,,--,-m,,w _nr-e,------,,-n-m w e e ,- e - w w r-e w e w-~ -r --,-----~,--remy-r, ---,y,----, -wr -s-w- w+w vm-wm- - - - ~ - g -
O Operations Summary July 1980 The following summary describes the significant operational activities during the reporting perfod. In support of this summary, a chronological log of significant events is included in this report. There were thirty-four Licensee Event Reports and one Special Report 80-2 on the positive moderator temperature coefficient. On 7-5-80, 0410,- operation began pulling rods for the approach to initial criticality. At 1040 on 7-5-80, the reactor reached initial criticality. There were scien reactor scrams during July of which two were manual scrams that occurred during low power physics tests. During July, all low power physics tests were completed. I i 1
~
.--n -
._,,e+ , - . , - . _ - - . , . -,_m-.., .-- - - - - , - - - ,-,..,,e,-r..-e. - - e - , , - - - , w-, - . , , , -,,,--_.w. y m.,--, -,. , , . -,e,, ~ -
Significant Operational Events Date Time Event 7/05/80 0410 Started pulling shutdown Rank A-rode to begin initial criticality. 7/05/80 1040 Initial criticality. 7/08/80 1532 A low power physics test manual reactor trip occurred. 7/08/80 2203 Tripped reactor for low power physics test. 7/08/80 2346 Reactor is in mode 2. 7/09/80 0913 Reactor was tripped manually. 7/09/80 2113 Reactor is critical. 7/11/80 1949 Reactor i, at 3% reactor power. 7/12/80 1951 Reactor trip was due to intermediate range nuclear instrumentation high flux trip. 7/13/80 0753 Started reducing power to hot zere power. 7/13/80 1225 Commenced rod withdrawal to bring reactor to 3% power. 7/13/80 1252 Reactor is at 3% power. 7/18/80 0717 Reactor trip was caused by turbine trip as a result of the P-1 interlock not being blocked below 10% power. 7/19/80 1212 Reactor is critical. 7/21/80 1905 Rolled the main turbine generator. 7/22/80 0108 The turbine generator was tied onto the TVA grid. 7/22/80 2349 Tripped main turbine generator. 7/23/80 1334 Decreasing reactor power in preparation for going to mode 4, 7/23/80 1914 Reactor trip was due to low steam generator level in #3 steam generator. 7/24/80 1847 Reactor coolant system is in mode 5. 2
. - ? . . _ _ .
O a AVERAGE DAILY UNIT POWER LEVEL
\
k' - DOCKET NO. 50-327 I UNIT DATE, 8-5-80 COMPLETED BY Frank M. Walker TELEPHONE (615) 842-0295
~
MONTH July 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net) (Mwe. Net) 1 0 17 0 2 0 ig o 3 0 g9 0 4 0 20 0 5 0 21 0 6 0 0 22 I 0 0 '.f 7, 23
* ~
8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 ;g o 13 0 0 29 14 0 0 30 m 15 0 3 J ,, _
.;_ . - .
. 16 0 :
INSTRUCTIONS ' " On this format. list the average daily unit power levelin MWe. Net for each day in the reporting inonth. Compute to the neareit whole megawatt. (4 /77) 3 I 1
. j ,
f \ - k OPERATING DATA REPORT
~
DOCKET NO. 50-327 DATE R-9-An COSIPLETED BY Fr= nte M- Walker TELEPHONE -(615) 842-0295 OPERATING STATUS Seanovah 1 N"I'5
- 1. Unit Name:
- 2. Reporting Period: July 1980
- 3. Licensed Thermal Power (31Wt): 170*
- 4. Nameplate Rating (Gross 31We): 1220.5 -- ~
- 5. Design Electrical Rating (Net StWe)- 1148
- 6. Sfaximum Dependable Capacity (Gross 31We): 1185
- 7. Sfaximum Dependable Capacity (Net alWe): 1148 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gi e Reason;:
- 9. Power Level To Which Restricted.If Any (Net alwe):
_ , _IO. Rnsons For Restrictions. If Any: *L w P wer Phvefee Tooeing
.s
'V- This afonth Yr..to.Date Cumulative
-- I1. Hours in Reporting Period 744 3672 3672
- 12. Number Of Hours Reactor Was Critical 371.81 371.81 371.81
- 13. Reactor Reserve Shutuown Hours 0 0 o
- 14. Hours Generator On-Line 18.35 18.35 Ig_3s
- 15. Unit Reserve Shutdown flours n n _ g
- 16. Gross Thermal Energy Generated (31WH) 12356.19 12356.19 12356.19 .
- 17. Gross Electrical Energy Generated (31WH) 230 , , ,
230 230 IS. Net Electrical Energy Generated (.\1WH) 0 0 0
- 19. Unit Service Factor NA NA NA
- 20. Unit Availability Factor NA - MA NA
- 21. Unit Capacity Factor (Using .\lDC Net) NA NA NA
- 22. Unit Capacity Factor (Using DER Net) NA _
NA NA
- 23. Unit Forced Outage Rate NA - MA . - -- _-WA---
~
~
- 24. Shutdowns Scheduled Over Nest 6.\1onths (Type. Date, and Duration of Each N '~vC-s i -12'_M "# Y ' A :'-'-
8-30 9-8-80 Outane to Inse=11 Hyd'ronen Tenitnrn in conrmin nd ~ ~
- -~
- 25. If Shur Down \t End Of Report Period, Estimated Date of Startup:- ,8-$-80"
, ] .
- 26. Units in Test Status f Prior to Commercial Operation):
~
Forecasr Achies ed ' ' ~ ~ ' ~ - ' INITIA L CRITICA LITY 7-4-80 7-5-80
,. INITIAL ELECTRICITY 8-21-80 7-22-80 CO\l\lERCIA L OPER ATION 10-3-80 4 (9/77)
, ,,w w - ~, n- g ~mn - -----
V
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UNil'Silull60WNS ANilPOWl:M Hlllik'llONS IH M'l 1:l' NO. 50-327 ,4?
,i UNil'NAntti hquoyah i l) Nil; R LRn .. ..
' ! COMPl.1lli D llY . frank .M._ Walker 't lli Pulfl AIONill 'Tuly 1980 'll 1.l l'IlONii
- (615).842r0295 .
_.. - . - _ .. = .- - - . - - - .
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Repins u m U hevent Recurrente d 7-8-80 S 6.52 B 2 NA ZZ ZZZZZ Low Power Physics Testing 7-8-80 S 1.71 B 2 NA ZZ ZZZZZ Low Power Physics Testing 1 7-12-80 F 10 A 3 NA TA INSTRUY Reactor Tripped Because I.R. High Flua
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Trip Exceeded Setpoint. Inst was 1 Checked and Found to be OK.
- 2 7-15-80 F 3.72 ,C 3 NA IA INSTRUR Recorders Used in Special Test were Connected Improperly. When Recorder
, was Turned on, the Over Temperature AT Tripped the Reactor.
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3 7-18-80 F 28.92 C 3 NA IA INSTRUE The P-1 Interlock was Open at 10%
- Power Causing Turbine Trip Which j . Caused a Reactor Trip. -
7-23-80 S 5.08 2 1111 SUPORTA Aux 'Feedwater Supports were not Seismi c j 4 Qualiffed. , 3 _ . _ . _ -. I 2 .1 4 1: I .n.eil Itc.c..n : klellanl: 8 1%InI>it G insuncilinis
*. N iintulcil A 1 guipnient 1.nlure (I spl.on) 1 -h14n nal fin Peep. nasion of Data '
ll Alaintenance os l'ett 2 hiannal Scs.un. I:nity Sheets for 1.icenwe < C.Hefueling .l. Automatic & sani. INent Repost (l.l:lO l'ile (NURI G-D Regniatory itestrisiion 4 Other (l!xplaud 0161) C' 1 Opciatos haining & I acmc 1:samination , IN Ailinunst rative 5 G Opcianonal I.nus (l'xplain) 1:sinbis 1 S.nne Source i pt/77) 11 Other (1:s pl.iin) ! I
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Pega 2 pf 2 e UNil Silulil0WNS ANI)l' owl:R RI;DUCllONS IMM:KET No, _ 5D:327 # 1-3' UNil' NAMl; Sequoya ilNIE 8-5-fl0 COMI'I.E llill ilY Frank M. Walker Rt.I'Olt l' MON ~lll ..luly 14An ;
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, - ; u i 4 7-23-80 F 196.76 G 3 NA IA INSTRUE A low-low Steam Generator Level Tripped Reactor in Process of Shutting Down
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$; N hvilnleil A l ignipineni l allnic (l'xplain) l M.ninal l~ns l'arp.nalle'n ol'l)ala Il M.iintenance ni l'est 1 M.ninal &s.nn. linsey Slieces lin I.ictmee C 1(cincling .I Antoniasic & s.un, 1%cna itep.n o (1 l'lO 1 ile INilld i; l a leer.nl.n"* 5 It* 8 81* t l"n l O'l*vi il $P Iilu n lill* l I i e st'esasi. lea 8Hinr. A 18+ rnse ladniludilon '
1 A.linsur.lialue 5 (. Upci.ilional 1 nos il spl.nn) I sint.it I S.nne Souice p8/1/) 11 Ollies tl splain)
- o Plant Maintenance Sungnary Balanced the number four reactor coolant pump.
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y Outage Maintena=ce Summary Inspected pipe hangers on safety related syscens inside and cutside ccatainment in accordance with a conformatica of actica letter free NRC and II bulletin 79-1/.. Repisced the steam valve room exhaust fans v-ith larger capacity fans. This was done to ensare that the steam valve room can be kept at 30 tp 120'T. 4 l s _ B
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