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| number = ML20059A001 | | number = ML20059A001 | ||
| issue date = 07/31/1990 | | issue date = 07/31/1990 | ||
| title = Monthly Operating Repts for Jul 1990 for Sequoyah Nuclear Plant Units 1 & 2 | | title = Monthly Operating Repts for Jul 1990 for Sequoyah Nuclear Plant Units 1 & 2 | ||
| author name = Hollomon T, Wallace E | | author name = Hollomon T, Wallace E | ||
| author affiliation = TENNESSEE VALLEY AUTHORITY | | author affiliation = TENNESSEE VALLEY AUTHORITY | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:. - . . . . . - | ||
t, -s. | |||
.1- . TENNESSEE VALLEY AUTHORITY | |||
.. SN 1578 Lookout Place-Chattanooga, Tennessee. 37402-2801 . | |||
August 15. 1990 | |||
* U.S. Nuclear' Regulatory Commission i ATTN: Document Control-Desk' Washington, D.C.- 20555. _ | |||
t Gentlemen: ) | |||
:In the Matter of )' Docket Nos. 50-327-- | |||
Tennessee Valley. Authority ;) 50-328' SEQUOYAH NUCLEAR'' PLANT (SQN) --JULY 1990 MONTHLY OPERATING REPORT: | |||
; Enclosed is the July 1990 Monthly Operating Roport as required by SQN Technical Specification 6.9.1.10.'' | |||
~ | |||
If:you have any questions concerning this ' matter, pier.se call M. A. Cooper at-(515)'843-6422. | |||
Very truly yours, TENNESSES' VALLEY AUTHORITY' a | |||
f$er"'"unussa E. G.-Wallace. Manager Nuclear Licensing and Regulatory Affairs Enclosure ' | |||
cc (Enclosure): | |||
INPO Records Center NRC Resident Inspector-Institute of Nuclear Power Operations Sequoyah Nuclear Plant i | |||
-1100 circle 75 Parkway, Suite 1500 2600 Igou Ferry Road, L Atlanta,. Georgia 30389 Soddy-Daisy, Tennessee 37379 Mr. J. N. Donohew Project Manager iRegional Administration - | |||
U.S. Nuclear. Regulatory Commission U.S., Nuclear Regulat'ory Commission One White Flint, North . Office.of' Inspection andtEnforcement 1 11555 Rockville Pike Region II Rockville, Maryland 20852 101 Marietta Streeta NW, Suite' 2900 1Atidnta, GeoEgia 30323 . | |||
Mr. B. D. Liaw.-Director TVA Projects. Division. Mr. B. ^.-Wilson, Project Chief One White Flint, North U.S. " ,..ar. Regulatory Commission I 11555 Rockville-Pike ' Region'. II Rockville, Maryland 20852 J101 Marietta Street NW,' Suite-2900 | |||
' Atlanta', Georgis 30323. j Mr. Ted Marston, Director Electric Power Research Institute. | |||
P.O. Box-10412 Palo~ Alto, California 94304 003220083 900731 " | |||
DR ADOCK 050'<0327 R PDC . | |||
~ | |||
s\\ | |||
;j An Equal Opportunity Employer . - | |||
1 | |||
! I' q i | |||
;. l | |||
. . l | |||
. TENNESSEE. VALLEY AUTHORITY NUCLEAR POWERIGROUP i SEQUOYAH NUCLEAR' PLANT . | |||
1 j | |||
i j | |||
MONTHLY OPERATING REPORT- l l | |||
1 | |||
- .TO THE-NUCLEAR. REGULATORY COMMISSION g | |||
'' JULY,1990 UNIT 1 ' | |||
DOCKET NUMBER.50-327 LICENSE NUMBER DPR-77 | |||
> 2 | |||
, UNIT 2- ' | |||
DOCKET NUMBER'50-328 LICENSE NUMBER'DPR-79 | |||
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OPERATIONAL | |||
==SUMMARY== | |||
JULY 1990 UNIT 1 r Unit 1 generated 838,200 MWh (gross) electrical power during July, with a capacity factor of 95.23 percent. . | |||
Unit 1 operated at approximately'100 percent reactor power level until 1816 Eastern daylight time (EDT) on' July 10, 1990, when the load war decreased ' | |||
f' 1. 140 MW, to 1,091 MW, to control condensate fluctuations. B-atring | |||
.5 was isolated because extractiori steam had been isolated when a pipe oss2k occurred on B-2 heater drain to No.-3 heater drain tank!(HDT). Unit 1-reactor power level was reduced cc..approximately 98 percent. Unit 1 was- [ | |||
returned to 100 percent reac'.or nowerflevel. at 0530 EDT on July 12, 1990.-- i Further= problems wera experienced with the No. 3 HDT pump; and on. . i July 30,- 1990 . at 12T)9 ~ EDT, the :eactor power level was again decreat approximately 98 percent. Unit 1 remained at.98 percent power level L _.n the'end of July. | |||
UNIT 2 Unit 2 generated 838,650 MWh (gross) electrical power during' July, with a capacity factor of 95.28 percent. Unit 2 operated at approximately 100 percent reactor power level until July 21, 1990, at 0736:EDT, when Unit 2 entered coastdown to-Unit 2 Cycle 4 refueling outage, uAt the end of July, Unit 2 was operating at approximately 91 percent' react r power level, f POWER-OPERATED RELIEF VALVES (?0RVs) AND SAFETY VALVES | |||
==SUMMARY== | |||
There were no challenges to PORVs or safety valves in the monthiof July. , | |||
l L | |||
OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during the month of July. ! | |||
t 4 | |||
I l | |||
l .1 | |||
l[ ' l. | |||
AVERACE DAILY UNIT. POWER LEVEL DOCKET NO. 50-327 UNIT,No.- One DATE: 02-90 , | |||
COMPLETED BY: T. J. Hollomon . TELEPHONE: (615)-843-7528 MONTH: JULY 1990-AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)' DAY (MWe-Net) 1 1016 17 1076 2 1107- '18 1107-3 1105 19 1107 4 1108 20 1075 5 1104 21' 1088 6 1105 22 1103- _; | |||
7 1076 23. 1103- i i | |||
8 1105 24 1104- ! | |||
9 1103 25 -1105 ' | |||
i i | |||
10 1093 26 1104 l' 11 1064 27 1105' t - ; | |||
l 12 1093 28 1103 i 13 1103 29 1103' | |||
: l. 14 1108 30 1091 15 1107 31 :-1074 , | |||
i 16 1088 1 L 1 f | |||
a i | |||
4- | |||
_, AVERAGE DAILY UNIT POWER LEVEL: | |||
DOCKET NO. 50-328 UNIT No. Two DATE 1 08-02-90 COMPLETED BY: T. J. Ho11omon TELEPHONE:' (615) 843-7528' MONTH: JULY 1990 AVERAGE DAILY: POWER LEVEL AVERAGE DAILY POWER LEVEL-DAY- (MWe-Net) DAY ~(MWe-Net) 1 1111 17 1109 2 '1111 18 1108 , | |||
3 1110 _ | |||
19 1107' 4 1111 20 1106' - | |||
5 1109 21 1097-6 1102 22 1085 ; | |||
7 1104 23 1074-8 1105 24 1068 9 1105 25 1061 10 1106 26 1053 , | |||
11 1102 27' ~1045 12 1091 28- 1035' i 13 1100 29 1029' 14 1103 30 :1016 _ | |||
15 1111 31 1009 , | |||
1 16 _ | |||
1107 1 | |||
i; 1 | |||
2- | |||
: , .1 | |||
,,,: . . OPERATING DATA REPORT | |||
- . = -. | |||
DOCKET NO. 50-327 | |||
. DATE Juount 3. 1990 COMPLETED BY T . 1. ' Holl omon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l- | |||
: 1. Unit Name: , Sanuovah Unit One j- lL | |||
: 2. Reporting Period:- .1ulv 1990 .l- l | |||
: 3. Licensed Thermal Power (MWt): 3411.0 l l-3 4 Nameplate Rating (Gross MWe): 1220.6 l. Jl_ | |||
: 5. Design Electrical Rating (Net HWe): 1148.0 .l l | |||
: 6. Maximum Dependable Capacity.(Gross MWe): 1183.0 l l- ; | |||
7.- Maximum Dependable Capacity (Not MWe): _1148.0 l l 'j | |||
: 8. If Changes Occur in Capacity Ratings.(Items Number 3 Through 7) Since Last Report, Give Reasons: | |||
N/A' f Power Level To Which RestricteJ. If Any (Net MWe): N/A | |||
: 10. Reasons For Restrictions, If Any: N/A | |||
. 1 This Month-- Yr-tr-Datei Cumulative , | |||
, i | |||
: 11. Hours in Reporting Period 744 -5.087 79.632' | |||
: 12. Number of Hours Reactor Was Critical 744.00 3.267.7 36.763 | |||
~ 13. Reactor Reserve Shutdown Hours 0 0 .- 0 | |||
: 14. Hours Generator On-Line 744.0 "3.167.1- 35.856.5 | |||
: 15. Unit Reserve Shutdown Hours 0.0 ' 0- 0 $ | |||
: 16. Gross Thermal Energy Generated (MWH)- 2.525.299.2- '10.205.044.5 116.540.924 ;I | |||
: 17. Gross Electrical Energy Generated (MWH) 838.200 3.474.930 39.498.686 i | |||
: 18. Het Electrical Energy Generated (MWH) 810.082 3.348.762- 37.820.791 } | |||
: 19. Unit Service Factor 100.0 62.3 45.0 '; | |||
: 20. Un(t Availability Factor 100.0 62.3 45.0- -l | |||
: 21. Unit Capacity Factor (Using MDC Net) 94.8 57.3- 41.4 | |||
: 22. Unit Capacity Factor (Using DER Net) 94.8 57.3. 41.4 , | |||
: 23. Unit Forced Outage Rate , 0.0 -2.2 47.1 | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date.' and Duration:of.Each): | |||
i | |||
: 25. If Shut Down At End Of Report Period Estimated Date of Startup: N/A' e | |||
o U. . | |||
fi - | |||
l *1 l , ,, OPERATING DATA REPORT DOCKET NO. 50-328 DATE Auoutt 3. 1990-COMPLETED BY T. J . Hollomon TELEPHONE-.f615) 843-7528 OPERATING STATUS l Notes l, 1 Unit Name: Seouovah Unit Two l l | |||
: 2. Reporting Period: July 1990 l_ l 3 | |||
: 3. Licensed Therwal Power (HWt): 3411.0 l l | |||
4 Nameplate Rating (Gross HWe): 1220.6 l l -- | |||
: 5. Design Electrical Rating-(Net HWe); - 1148.0' -l l | |||
: 6. Maximum Dependable Ca'pacity (Gross HWe): 1183.0 , l ;l- | |||
: 7. Maximum Dependable Capacity (Net HWe): 1148.0 l 1 | |||
: 8. -If Changes occur in Capacity Ratings (Items Number 3 Throigh 7, Since Last Report. Give Reasons: | |||
N/A . | |||
Jl l | |||
: 9. Power Level To Which Restricted,'If Any (Net MWe): N/A | |||
: 10. Reasons for Restrictions, If Any: N/A fj This Month- 's-to-Cate Cumulative ! | |||
: 11. Hours in Reporting Period 744 5.087 71:592 ( | |||
: 12. Number of Hours Reactor Was Critical 744,0 5.059.9 3a . 500 - ! | |||
: 13. Reactor Reserve Shutdown Hours 0 0 -0' | |||
: 14. Hours Generator On-Line 744.0 5.048.'4I 37.744.2 | |||
: 15. Unit Reserve Shutdown Hours 0.0 0' ' | |||
0- | |||
: 16. Gross Thermal Energy Generated (MWH)- 2.487.332.6 16.'825.176.6' 117.235.437- | |||
: 17. Gross Electrical Energy Generated (HWH) 838.650 | |||
: 18. Net Electrical Energy. Generated (MWH) 5.773.850 3 794.646 808.420 5.563.475 '38.011.809 | |||
: 19. Unit Service Factor '100.0~ 99.2 -52.7 | |||
: 20. Unit Availability Factor j | |||
'. 0 0 . 0 99.2 '52;7 i | |||
: 21. Ur!', Capacity Factor (Using HDC Net) 94.7 95.3 46.3- | |||
: 22. Unit Capacity Factor (Using DER Net) ,j 94.7 95.3 46.3 :j | |||
: 23. Unit Forced Outage Rate , 0.0 0.8 * | |||
=41.5-l | |||
: 24. Shutdowns Scheduled Over Next 6 Honths (Type. Date. 'and Duration of Each): . | |||
Unit 2 Cvele 4' refuelina outaas is scheduled for Sootember 1990 with a duration of;70 ' dawn. l i | |||
-j i | |||
: 25. If Shut Dom ^. i nd Of Report Period ' Estimated Date of- Startup: N/A j | |||
i y | |||
y 1 | |||
4 i | |||
.q | |||
b= | |||
6 DOCKET NO:.._. 59 327 UNIT SHUlDOWNS AND POWER REDUCTIONS UNii NAid: Qag__ _,_,,, | |||
DATE:__.DD/Dfd90. _ , | |||
REPORT MONIH: July 1990 _ COMPLETED BY:T. J. Ho].lgebn-TELEPPONE:(6151 843-7528 Method of Licensee Cause and Corrective . - | |||
* Shutting Down Event Action to Duration Systgm Compgnent Type I Reason Reactor3 Report No. Code Code Prevent Recurrence 'l No. Date (Hours) l 6 900710 F A 5 At 1816 (EDT) on 7/10/90 B-string heater was isolated because of extraction steam isolation when a break occurred on B-2 heater drain to No. 3 HDT. | |||
Power was reduced to | |||
'l approximately 98 percent. | |||
Unit I was at 100 percent reactor power level again on 7/12/90, at 0530 (EDI). | |||
A 5 At 1259 (EDT) on 7/30/90, 7 900730- F reactor power level again was reduced to approximately 98 percent to reduce No.-3 HDT pump flow to increase delta P. | |||
B-string heaters 2. 3. and 4 were isolated to repair leaks. | |||
Unit-I was operating at 98 percent reactor power on 7/31/90 at 2400 (EDT). | |||
4 Exhibit G-Instructions I:F forced 2 Reason: 3 Method: | |||
I-Manual for Preparation of Data 5: Scheduled A-Eqripment failure (Explain) | |||
B-Maihtenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage ( NOREG-061 ) | |||
E-Operator Training and License Examination 5-Reduction e F-Administrativa 9-Other G-Operational Error (Explain) SExhibit I-Same Source H-Other (Explair:) | |||
_. _.._,_.m | |||
._ .,_,_,.._q. _ | |||
- ,__a.. .i.w.ms m_, ___ | |||
___m.m. ,-. | |||
.i- | |||
+ | |||
-s DOCKET NO: SL328 '' | |||
UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME: swo .[' | |||
DATE: 08/06/90 REPORT MONTH: July 1990 COMPLETED BY:T. J. Hollomon IELEPHONE:f6151 843-1528 , - | |||
* Method of ticensee Cause and Corrective Duration Shutting Down Event Systp Cognent Action to No. Date Type 3 (Hours) Rtison 2 Reactor 3 Report No. Code Code Prevent Recurrence Unit 2 entered coastdown to Cycle 4 refueling outage at 0736 (EDT) on 7/21/93 and was operating at approminutely 91 perr.ent reactor power -level on 7/31/90. | |||
Forced 2 Reason: 4 | |||
'3 Method: Exhibit G-Instructions 5: Scheduled 'A-Equipment Failure (Expeain) 1-N nual for Preparation of Data- | |||
. B-Nintenance or Test 2-m nual Scram Entry sheets' for Licensee C-Ref uel ing : . Automatic Scram ' Event Report (LER)'Eile D-Regulatory Restruction | |||
.. 4-Continuation'of. Existing Outage (NUREG-061) | |||
-E-Operator Training and License Examination 5-Reduction | |||
' F-Administrative . | |||
9-ether G-Operational Error. (Explain) | |||
-5 Exhibit I-Same Source H-Other (Explain) . | |||
-- i i.-.~... ':w l _ - . = = - . _ . .L.-. .ux. . L: .~ . | |||
-.}} |
Latest revision as of 22:47, 6 January 2021
ML20059A001 | |
Person / Time | |
---|---|
Site: | Sequoyah ![]() |
Issue date: | 07/31/1990 |
From: | Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9008220085 | |
Download: ML20059A001 (9) | |
Text
. - . . . . . -
t, -s.
.1- . TENNESSEE VALLEY AUTHORITY
.. SN 1578 Lookout Place-Chattanooga, Tennessee. 37402-2801 .
August 15. 1990
- U.S. Nuclear' Regulatory Commission i ATTN: Document Control-Desk' Washington, D.C.- 20555. _
t Gentlemen: )
- In the Matter of )' Docket Nos. 50-327--
Tennessee Valley. Authority ;) 50-328' SEQUOYAH NUCLEAR PLANT (SQN) --JULY 1990 MONTHLY OPERATING REPORT:
- Enclosed is the July 1990 Monthly Operating Roport as required by SQN Technical Specification 6.9.1.10.
~
If:you have any questions concerning this ' matter, pier.se call M. A. Cooper at-(515)'843-6422.
Very truly yours, TENNESSES' VALLEY AUTHORITY' a
f$er"'"unussa E. G.-Wallace. Manager Nuclear Licensing and Regulatory Affairs Enclosure '
cc (Enclosure):
INPO Records Center NRC Resident Inspector-Institute of Nuclear Power Operations Sequoyah Nuclear Plant i
-1100 circle 75 Parkway, Suite 1500 2600 Igou Ferry Road, L Atlanta,. Georgia 30389 Soddy-Daisy, Tennessee 37379 Mr. J. N. Donohew Project Manager iRegional Administration -
U.S. Nuclear. Regulatory Commission U.S., Nuclear Regulat'ory Commission One White Flint, North . Office.of' Inspection andtEnforcement 1 11555 Rockville Pike Region II Rockville, Maryland 20852 101 Marietta Streeta NW, Suite' 2900 1Atidnta, GeoEgia 30323 .
Mr. B. D. Liaw.-Director TVA Projects. Division. Mr. B. ^.-Wilson, Project Chief One White Flint, North U.S. " ,..ar. Regulatory Commission I 11555 Rockville-Pike ' Region'. II Rockville, Maryland 20852 J101 Marietta Street NW,' Suite-2900
' Atlanta', Georgis 30323. j Mr. Ted Marston, Director Electric Power Research Institute.
P.O. Box-10412 Palo~ Alto, California 94304 003220083 900731 "
DR ADOCK 050'<0327 R PDC .
~
s\\
- j An Equal Opportunity Employer . -
1
! I' q i
- . l
. . l
. TENNESSEE. VALLEY AUTHORITY NUCLEAR POWERIGROUP i SEQUOYAH NUCLEAR' PLANT .
1 j
i j
MONTHLY OPERATING REPORT- l l
1
- .TO THE-NUCLEAR. REGULATORY COMMISSION g
JULY,1990 UNIT 1 '
DOCKET NUMBER.50-327 LICENSE NUMBER DPR-77
> 2
, UNIT 2- '
DOCKET NUMBER'50-328 LICENSE NUMBER'DPR-79
- }
4
'?
< .5 i
i l
1
-,n , ,. ,. #
g
=, ; : *.
OPERATIONAL
SUMMARY
JULY 1990 UNIT 1 r Unit 1 generated 838,200 MWh (gross) electrical power during July, with a capacity factor of 95.23 percent. .
Unit 1 operated at approximately'100 percent reactor power level until 1816 Eastern daylight time (EDT) on' July 10, 1990, when the load war decreased '
f' 1. 140 MW, to 1,091 MW, to control condensate fluctuations. B-atring
.5 was isolated because extractiori steam had been isolated when a pipe oss2k occurred on B-2 heater drain to No.-3 heater drain tank!(HDT). Unit 1-reactor power level was reduced cc..approximately 98 percent. Unit 1 was- [
returned to 100 percent reac'.or nowerflevel. at 0530 EDT on July 12, 1990.-- i Further= problems wera experienced with the No. 3 HDT pump; and on. . i July 30,- 1990 . at 12T)9 ~ EDT, the :eactor power level was again decreat approximately 98 percent. Unit 1 remained at.98 percent power level L _.n the'end of July.
UNIT 2 Unit 2 generated 838,650 MWh (gross) electrical power during' July, with a capacity factor of 95.28 percent. Unit 2 operated at approximately 100 percent reactor power level until July 21, 1990, at 0736:EDT, when Unit 2 entered coastdown to-Unit 2 Cycle 4 refueling outage, uAt the end of July, Unit 2 was operating at approximately 91 percent' react r power level, f POWER-OPERATED RELIEF VALVES (?0RVs) AND SAFETY VALVES
SUMMARY
There were no challenges to PORVs or safety valves in the monthiof July. ,
l L
OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during the month of July. !
t 4
I l
l .1
l[ ' l.
AVERACE DAILY UNIT. POWER LEVEL DOCKET NO. 50-327 UNIT,No.- One DATE: 02-90 ,
COMPLETED BY: T. J. Hollomon . TELEPHONE: (615)-843-7528 MONTH: JULY 1990-AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)' DAY (MWe-Net) 1 1016 17 1076 2 1107- '18 1107-3 1105 19 1107 4 1108 20 1075 5 1104 21' 1088 6 1105 22 1103- _;
7 1076 23. 1103- i i
8 1105 24 1104- !
9 1103 25 -1105 '
i i
10 1093 26 1104 l' 11 1064 27 1105' t - ;
l 12 1093 28 1103 i 13 1103 29 1103'
- l. 14 1108 30 1091 15 1107 31 :-1074 ,
i 16 1088 1 L 1 f
a i
4-
_, AVERAGE DAILY UNIT POWER LEVEL:
DOCKET NO. 50-328 UNIT No. Two DATE 1 08-02-90 COMPLETED BY: T. J. Ho11omon TELEPHONE:' (615) 843-7528' MONTH: JULY 1990 AVERAGE DAILY: POWER LEVEL AVERAGE DAILY POWER LEVEL-DAY- (MWe-Net) DAY ~(MWe-Net) 1 1111 17 1109 2 '1111 18 1108 ,
3 1110 _
19 1107' 4 1111 20 1106' -
5 1109 21 1097-6 1102 22 1085 ;
7 1104 23 1074-8 1105 24 1068 9 1105 25 1061 10 1106 26 1053 ,
11 1102 27' ~1045 12 1091 28- 1035' i 13 1100 29 1029' 14 1103 30 :1016 _
15 1111 31 1009 ,
1 16 _
1107 1
i; 1
2-
- , .1
,,,: . . OPERATING DATA REPORT
- . = -.
DOCKET NO. 50-327
. DATE Juount 3. 1990 COMPLETED BY T . 1. ' Holl omon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l-
- 1. Unit Name: , Sanuovah Unit One j- lL
- 2. Reporting Period:- .1ulv 1990 .l- l
- 3. Licensed Thermal Power (MWt): 3411.0 l l-3 4 Nameplate Rating (Gross MWe): 1220.6 l. Jl_
- 5. Design Electrical Rating (Net HWe): 1148.0 .l l
- 6. Maximum Dependable Capacity.(Gross MWe): 1183.0 l l- ;
7.- Maximum Dependable Capacity (Not MWe): _1148.0 l l 'j
- 8. If Changes Occur in Capacity Ratings.(Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A' f Power Level To Which RestricteJ. If Any (Net MWe): N/A
- 10. Reasons For Restrictions, If Any: N/A
. 1 This Month-- Yr-tr-Datei Cumulative ,
, i
- 11. Hours in Reporting Period 744 -5.087 79.632'
- 12. Number of Hours Reactor Was Critical 744.00 3.267.7 36.763
~ 13. Reactor Reserve Shutdown Hours 0 0 .- 0
- 14. Hours Generator On-Line 744.0 "3.167.1- 35.856.5
- 15. Unit Reserve Shutdown Hours 0.0 ' 0- 0 $
- 16. Gross Thermal Energy Generated (MWH)- 2.525.299.2- '10.205.044.5 116.540.924 ;I
- 17. Gross Electrical Energy Generated (MWH) 838.200 3.474.930 39.498.686 i
- 18. Het Electrical Energy Generated (MWH) 810.082 3.348.762- 37.820.791 }
- 19. Unit Service Factor 100.0 62.3 45.0 ';
- 20. Un(t Availability Factor 100.0 62.3 45.0- -l
- 21. Unit Capacity Factor (Using MDC Net) 94.8 57.3- 41.4
- 22. Unit Capacity Factor (Using DER Net) 94.8 57.3. 41.4 ,
- 23. Unit Forced Outage Rate , 0.0 -2.2 47.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date.' and Duration:of.Each):
i
- 25. If Shut Down At End Of Report Period Estimated Date of Startup: N/A' e
o U. .
fi -
l *1 l , ,, OPERATING DATA REPORT DOCKET NO. 50-328 DATE Auoutt 3. 1990-COMPLETED BY T. J . Hollomon TELEPHONE-.f615) 843-7528 OPERATING STATUS l Notes l, 1 Unit Name: Seouovah Unit Two l l
- 2. Reporting Period: July 1990 l_ l 3
- 3. Licensed Therwal Power (HWt): 3411.0 l l
4 Nameplate Rating (Gross HWe): 1220.6 l l --
- 5. Design Electrical Rating-(Net HWe); - 1148.0' -l l
- 6. Maximum Dependable Ca'pacity (Gross HWe): 1183.0 , l ;l-
- 7. Maximum Dependable Capacity (Net HWe): 1148.0 l 1
- 8. -If Changes occur in Capacity Ratings (Items Number 3 Throigh 7, Since Last Report. Give Reasons:
N/A .
Jl l
- 9. Power Level To Which Restricted,'If Any (Net MWe): N/A
- 10. Reasons for Restrictions, If Any: N/A fj This Month- 's-to-Cate Cumulative !
- 11. Hours in Reporting Period 744 5.087 71:592 (
- 12. Number of Hours Reactor Was Critical 744,0 5.059.9 3a . 500 - !
- 13. Reactor Reserve Shutdown Hours 0 0 -0'
- 14. Hours Generator On-Line 744.0 5.048.'4I 37.744.2
- 15. Unit Reserve Shutdown Hours 0.0 0' '
0-
- 16. Gross Thermal Energy Generated (MWH)- 2.487.332.6 16.'825.176.6' 117.235.437-
- 17. Gross Electrical Energy Generated (HWH) 838.650
- 18. Net Electrical Energy. Generated (MWH) 5.773.850 3 794.646 808.420 5.563.475 '38.011.809
- 19. Unit Service Factor '100.0~ 99.2 -52.7
- 20. Unit Availability Factor j
'. 0 0 . 0 99.2 '52;7 i
- 21. Ur!', Capacity Factor (Using HDC Net) 94.7 95.3 46.3-
- 22. Unit Capacity Factor (Using DER Net) ,j 94.7 95.3 46.3 :j
- 23. Unit Forced Outage Rate , 0.0 0.8 *
=41.5-l
- 24. Shutdowns Scheduled Over Next 6 Honths (Type. Date. 'and Duration of Each): .
Unit 2 Cvele 4' refuelina outaas is scheduled for Sootember 1990 with a duration of;70 ' dawn. l i
-j i
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6 DOCKET NO:.._. 59 327 UNIT SHUlDOWNS AND POWER REDUCTIONS UNii NAid: Qag__ _,_,,,
DATE:__.DD/Dfd90. _ ,
REPORT MONIH: July 1990 _ COMPLETED BY:T. J. Ho].lgebn-TELEPPONE:(6151 843-7528 Method of Licensee Cause and Corrective . -
- Shutting Down Event Action to Duration Systgm Compgnent Type I Reason Reactor3 Report No. Code Code Prevent Recurrence 'l No. Date (Hours) l 6 900710 F A 5 At 1816 (EDT) on 7/10/90 B-string heater was isolated because of extraction steam isolation when a break occurred on B-2 heater drain to No. 3 HDT.
Power was reduced to
'l approximately 98 percent.
Unit I was at 100 percent reactor power level again on 7/12/90, at 0530 (EDI).
A 5 At 1259 (EDT) on 7/30/90, 7 900730- F reactor power level again was reduced to approximately 98 percent to reduce No.-3 HDT pump flow to increase delta P.
B-string heaters 2. 3. and 4 were isolated to repair leaks.
Unit-I was operating at 98 percent reactor power on 7/31/90 at 2400 (EDT).
4 Exhibit G-Instructions I:F forced 2 Reason: 3 Method:
I-Manual for Preparation of Data 5: Scheduled A-Eqripment failure (Explain)
B-Maihtenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage ( NOREG-061 )
E-Operator Training and License Examination 5-Reduction e F-Administrativa 9-Other G-Operational Error (Explain) SExhibit I-Same Source H-Other (Explair:)
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-s DOCKET NO: SL328
UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME: swo .['
DATE: 08/06/90 REPORT MONTH: July 1990 COMPLETED BY:T. J. Hollomon IELEPHONE:f6151 843-1528 , -
- Method of ticensee Cause and Corrective Duration Shutting Down Event Systp Cognent Action to No. Date Type 3 (Hours) Rtison 2 Reactor 3 Report No. Code Code Prevent Recurrence Unit 2 entered coastdown to Cycle 4 refueling outage at 0736 (EDT) on 7/21/93 and was operating at approminutely 91 perr.ent reactor power -level on 7/31/90.
Forced 2 Reason: 4
'3 Method: Exhibit G-Instructions 5: Scheduled 'A-Equipment Failure (Expeain) 1-N nual for Preparation of Data-
. B-Nintenance or Test 2-m nual Scram Entry sheets' for Licensee C-Ref uel ing : . Automatic Scram ' Event Report (LER)'Eile D-Regulatory Restruction
.. 4-Continuation'of. Existing Outage (NUREG-061)
-E-Operator Training and License Examination 5-Reduction
' F-Administrative .
9-ether G-Operational Error. (Explain)
-5 Exhibit I-Same Source H-Other (Explain) .
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