ML20058M806: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
Line 2: | Line 2: | ||
| number = ML20058M806 | | number = ML20058M806 | ||
| issue date = 11/30/1993 | | issue date = 11/30/1993 | ||
| title = Monthly Operating Repts for Nov 1993 for Sequoyah Plant Units 1 & 2 | | title = Monthly Operating Repts for Nov 1993 for Sequoyah Plant Units 1 & 2 | ||
| author name = Fenech R, Hollomon T | | author name = Fenech R, Hollomon T | ||
| author affiliation = TENNESSEE VALLEY AUTHORITY | | author affiliation = TENNESSEE VALLEY AUTHORITY |
Latest revision as of 23:10, 6 January 2021
ML20058M806 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 11/30/1993 |
From: | Fenech R, Hollomon T TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9312210112 | |
Download: ML20058M806 (11) | |
Text
v-
,o 4 A
l Tennessee Va4ey Autnonty. Post Offce fb 20'XL Soddy Daisy. Tenressee 373797J00 i
i Robert A. Fenech v.c eaesdent seaaayuh Nxcar Pielt j
December 14, 1993 U.S. Nuclear Regulatory Commission AT1W: Document Control Desk Washington, D.C. 20555 l
l Gentlemen:
In the Matter of ) Docket Nos. 50-327 :
Tennessee Valley Author 3.ty ) 50-328 SEQUOYAH NUCLEAR PLANT OiQN) - NOVEMBER 1993 MONTHLY OPERATING REPORT Enclosed is the November 1993 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10. .
If you have any questions concerning this matter, please. call J. W. Proffitt at (615) 843-6651.
Sincerely. -
d Robert A. Fenech Enclosure cc: See page 2 1
1- l
- 2100 0 ,
1 l
9312210112 931130 5
g (( h gDR ADOCK0500g7 g / >
l
~
1' .
t.
1 I i l' U.S. Nuclear Regulatory Commission .l Page 2 ,i December.14, 1993 cc (Enclosure): )
INPO Records Center <
Institute of Nuclear Power OperationsL y, 700 Calleria Parkway. !
Atlanta, Georgia 30339-5957: :l t
Mr. D. E. LaBarge, Project Manager
- U.S. . Nuclear Regulatory Conunission ' .j One White Flint, North:
11555 Rockville' Pike y Rockville, Maryland 20852-2739-Mr. Ted Marston,. Director Electric Power Research' Institute 7j P.O. Box 10412 Palo Alto, California 94304 i NRC Resident Inspector -l Sequoyah Nuclear Plant ,
2600 I?,ou Ferry Road '1 Soddy-Daisy, Tennessee 37379-3624-Regional Administration U.S. Nuclear Regulatory Conunission Office of Inspection and Enforcement Region II ~
101 Marietta Street, NW, Suite 2900 'i Atlanta, Georgia 30323-2711 :
1 Regional Administrator l U.S. Nuclear Regulatory Conunission ]
Region II 'l l 101 Marietta Street, NW, Suite 2900 1 Atlanta, Georgia 30323-2711- 1 i
Mr. F. Yost, Director Research Services Ij Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006-3800 I
l l :
e l, Y
b
.p' :s
. . e 4 .!
l 4
)
3 1
1 1
r TEMEESSEE VALLEY AUTHORITY ~!
9 NUCLEAR POWER GROUP ;
SEQUDYAE NUCLEAR FIANT .)
! i i
I I '
IRAITELY OPERATINC REPORT. i TU THE NUCIEAR REGUIATURY C0fftISSI(38 l NOFEftBER 1993 i
I UNIT 1 l .
~
I DOCERT NtfIBER 50-327 'i LICENSE NtftBER DPR-77.
! t i 1 i
l UNIT 2 I
6 DOCEET NIEtBER 50-328 l
LICENSE NUttBER DPR-79 1
l 1
l t
OPERATIONAL
SUMMARY
NOVEMBER 1993
. UNIT 1
! The Unit 1 Cycle 6 refueling outage continued. Unit I remained in Mode 5 at the end of November.
UNIT 2 l Unit 2 generated 468,680 megawatthours (MWh) (gross) electrical power
! during November with a capacity factor of 56.02 percent. Unit 2 was operating at approximately 49 percent reactor power and increasing at the beginning of November and reached 100 percent reactor power on November 5 at 0545 EST.
At 2115 EST on November 5, a power level decrease to 30 percent was initiated to allow repairs on the excitation system to be performed. On Novesber 8 at 1921 EST, the Unit 2 generator was removed from the grid for exciter work.
Unit 2 was returned to service on November 10 at 0417 EST when the generator was tied to the grid. Reactor power level was at approximately 25 percent.
Unit 2 reached 100 percent reactor power on November 12 at 0557 EST.
On November 16 at 0913 EST, a reactor shutdown to Mode'4 was initiated as a l result of thermal barrier check valve issues. At 2217 EST that day, the unit vas removed from the grid. Unit 2 entered Mode 2 at 2245 EST and entered l
Mode 3 at 2330 EST on November 16. Unit 2 entered Mode 4 on November 17 at 1847 EST.
On November 20, startup was initiated. Unit 2 entered Mode 3 on November 22 l at 0132 EST, and the reactor was taken critical at 1814 EST.that day. Urdt 2 entered Mode 1 on November 23 at 0256 EST and was returned to service that day at 0852 EST when the generator was tied to the grid. Unit 2 reached 100 percent reactor power on November 27 at 0340 EST.
Unit 2 was operating at 100 percent reactor power at the end of November.
l l
l l
l
4 i
AVERACE IIAILY UNIT POWR LEVEL DOCKET NO. 50-327' UNIT No. One DATE:- 12-04-93 COMPLETED BY: T. J, Hollomon TELEPHONE: '(615) 843-7528 l MONTH: NOVEMBER 1993 i
i AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL- !
pH (MWe-Net) DM (MWe-Net) -j i
-i 1 -1 '17 '-28 ;
i 2 -1 -18 -19 3 -5 19 -16 ;
4 -2 20 -19 !
5 -2 21 -23 ,
i 6 -2 22 -33 7 -2 23- l 8 -16 24 _ -1 .!
i 9 -26 25 -1 ;
10 -16 26 -1 11 -2 27 -1 4
'i
-i 12 -1 28 -1 1 13 -2 29' -1 14 -1 30 15 -1 31 N/A 16 -7 -
l ll
.. j
.j
.1
. i
- l
-i AVERAGE MILY llNIT POWER LEVEL j DOCKET NO. 50-328 UNIT No. 'Two vale: 12-04-93 ,
COMPLETED BY: T. J. Hollomon TELEPHONE: (615) 843-7528' l i
MONTH: NOVEMBER 1993 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL i DAY (MWe-Net) I DAY Q9(e-Net)-
1 1167 17- -2 2 820 18 -5 !
3 894 ~19- -5 4 1058 20 -2 5 1114 21 -5 t
6 527 12 2 7 421 23 124 i 8 277 24 386 $
9 -2 ,_ 25 623 10 266 26' 695 11 858 27 1130 i
12 1109 28 1133 l, 13 1124 29 1131 .
14 1126 30 1125' !
i 15 1128 31 N/A 16 762 l
l
-i l
'I
?
.. ., c -j
. OPERATING DATA REPORT -i DOCKET NO. _50-327'- .i DATE 12/04/93 4 COMPLETED BY:. T. J. Hollomon i iTELEPHONE'- (6151 843-7528 f i
QEf, RATING STATUS l Notes .- l- e
- 1. Unit Name: _ 1gguoyah Unit One -l. l'
- 2. Reporting Period: November 1993' l l. .l
- 3. Licensed Thermal Power (MWt): 3411.0 l 1l; l
- 4. Nameplate Rating (Gross MWe): _1220.6 l. ll l
- 5. Design Electrical Rating (Net MWe): 1148.0 l- .l ;j l
- 6. Maximum Dependable Capacity (Gross MWe): 1162.0' l -- l j
.l l 7. Maximum Dependable Capacity (Net MWe): 1122.0 l
- 8. If Changes Occur in Capacity Ratings (Item Numbers 31hrough 7) Since'Last' Report,?Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe): N/A 5
- 10. Reasons For Restrictions, If Any: N/A 3 a
l This Month Yr-to-Date CumulativeL
- 11. Hours in Reporting Period -720 -8.016- 108.865 c
- 12. Number of Hours Reactor Was Critical 0' 1.281.3~ 56.029 '!
- 13. Reactor Reserve Shutdown Hours 0 0 0 l
- 14. Hours Generator On-Line 0- '1.220.6- 54.828.5 !
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH)' 0 3.915.909.5 '
178.893.754 !
- 17. Gross Electrical Energy Generated (MWH) 0 1.358.540 60.702.654
- 18. Het Electrical Energy Generated (IMI) -6.048~ -1.248.787: 58:171.009~ 'j
- 19. Unit Service Factor 0 15.2 50.4 .{
- 20. Unit Availability Factor 0 '15.2 ' 50.4> j
- 21. Unit Capacity Factor (Using MDC Net). 13.9'
-0.7 '47.6'
- 22. Unit Capacity Factor (Using DER Net) -Os 7 13.6 46.5
- 23. Unit Forced Outage Rate 0 47.5' 38.7
- 24. Shutdowns Scheduled Over Neat 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: February 1. 1994' l
1 i
.j 1
I l
l l
j i
r
, i g +. , y .%'J h J r
i h
t OPERATING DATA REPORT l
I DOCKET ~NO. _10-J28 ,
'DATE 12/04/93
' COMPLETED BY 1. J. Hollomon TELEPHONE f6151 843-7528 I
(
l Of1FA11NG STATUS l Notes l
- 1. Unit Name: ..Seavoyah Unit Two l 'l' i 2. Reporting Period: November 1993 l l
- 3. Licensed Thermal Power (HWt): 3411.0 l l l 4. Nameplate Rating (Gross HWe): 1220.6 l -l '
l S. Design Electrical Rating (Net HWe): 1148.0 l l
- 6. Maximum Dependable Capacity (Gross HWe): 1162.0 l' ,l l 7. Maximum Dependable Capacity (Net HWe): 1122.0 l l 3
- 8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
W 7
I 9. Power Level To Which Restricted If Any (Net HWe): N/A
- 10. Reasons for Restrictions, If Any: N/A ,
This Month .Yr-to-Date' Cumulative
- 11. Hours in Reporting Period 720 8.016 100.825
- 12. Number of Hours Acactor Was Cr;tical 581.3 2.068.3 58.281
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 532.5 1;801.3 56.878.7
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (HWH) 1.401.901.4 5.312.980.0 178.494.759 '
- 17. Gross Electrical Energy Generated (HWH) 468.680 1.785.463 60.508.582
- 18. Net Electrical Energy Generated (HWH) 448.190 1.661.627 57.876.902
- 19. Unit Service Factor __ 74.0 22.5 56.4
- 20. Unit Availability Factor 74.0 22.5 56.4
- 21. Unit Capacity Factor (Using HDC Net) 55.5 18.5 51.2
- 22. Unit Capacity Factor (Using DER Net) 54.2 18.1 50.0
- 23. Unit Forced Outage Rate 2fiQ___ 77.5 37.1
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
Unit 2 Cvele 6 Refuelino Outtge. April 1. 1994. 65' Days
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: j l
1
d-DOCKET NO: 50-327 o UNIT SWJTDOWHS AND POWER REDUCTIONS UNIT NAME: One .
DATE: 12/03/93 "
REPORY NONTH: November 1993 COMPLETED BY:T. J. Hollomon TELEPHONE:f6151 843-7528 Method of Licensee Cause and Corrective 1 Duration Shutting Down Event System Comp nent Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report No. Code 4
Code Prevent Recurrence 4 931101 5 720 C 4 N/A N/A N/A The Unit 1 Cycle 6 refueling outage continued.
- F: Forced; 2 Reason 3Method:
. ..dExhibit G-Instructions. ,
5: Scheduled- A-Equipment Failure (Explain) 1-Manual .for Preparation of Data 8-Maintenance'or Test- l2-Manual Scram- ' Entry sheets for Licensee-C-Refueling -
,3-Automatic Scram Event Report (LER) File.~ ,.
D-Regulatory Restruction' 4-Continuation of. Existing Outage '(NUREG-lO22)
E-Operator. Training and -License Examination 5-Reduction .-.
F-Administrative 9-Other-5 G-Operational Error (Explain) Exhibit I-Same' Source J
. H-Other . (Explain) '.
~~-.___..._.;..n.._.......
._._.c. ._._._...-.._..__; . __. . . , _ _ . . . . . _ , .;_.-.-.._. .. - , . .
00CXET NO: 50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: Two ,
DATE: 12/03/93 REPORT NONTH: November 1993 COMPLETED BY:7. J. Hollomon TELEPHONE:f615) 843-7528 Method of Licensee Cause and Corrective Ouration Shutting Down Event System Compgnent Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report No. Code 4
Code Prevent Recurrence ,
5 931101 F B 4 N/A N/A N/A At the beginning of November, Unit 2 was increasing power after an outage for voltage regulator repairs. l Unit 2 reached 100 percent power on November 5 at 0545 EST. .
6 931105 F 4.6 B 5 N/A At 2115 EST on November 5,' a reactor !
power decrease to 30 percent was 1 initiated to allow excitation system repairs to be performed. On November 8 at .1921 EST, the Unit- 2 generator was removed from the grid i for exciter work. Problems with the compensator card, minimum excitation L limitor card, transformer card, and logic drawer were identified. These components were replaced and the system was tested and determined to operable. Unit 2 was returned to service on November 10 at 0417 EST when the generator was once again tied to .the grid. Reactor power level was at approximately 25 per-cent. Unit 2 reached 100 percent 4 reactor power on November 12 at . 1 0557 EST.
7 931116 F 21.5 B 1 327/93029 CC 1SV On November 16 at 0913 EST, a reactor shutdown to Mode 4 was initiated as a result of a thermal barrier check valve issue. Seven of the eight check valves were stuck in the open position. The cause of the condition was oxide wedging (iron oxide corrosion build--up) between valve components (piston and bonnet). The valves were 2 Reason: 3 Hethod: 4 I:F Forced Exhibit G-Instructions 5: Scheduled .A-Equipment Failure (Explain) 1-Mandal for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Re fueling 3-Automatic Scram Event Report (LER) File D-Regulatery Restruction ' 4-Continuation of Existing Outage. (NUREG-1022) ;
-E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other 5
G-Operational Erro? (Explain) Exhibit I-Same Source H-Other (Explain) j
DOCKET NO: 50-328 UNIT SHUTDOWNS AND 10WER REDUCTIONS UNIT NAME: Two .
DATE: 12/03/ E,__
REPORT MONTH: November 1993 COMPLETED BV:T. 1 Mallamon
- TELEPHONE:(6151 843-7528 Method of Licensee Cause and Corrective Duration Shutting Down Event System Component Action to No. Date Type l Reason 2 Reactor 3 Report No. Code 4
Code 5 Prevent Recurrence (Hou rs) ,
7 931116 F 21.5 B 1 327/93029 CC ISV disassembled, cleaned, repaired, and cont. returned to service. A long-term action plan is being developed to ensure continued check valve oper-ability. Unit 2 entered Mode 1 on November 23 at 0256 EST and was returned to service.
'I F: Forced '2 Reason: 3 Method: 4 Exhibit G-Instructions S: Scheduled 'A-Equipment Failure (Explain) -l-Manual for Preparation of Data B-Maintenance 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 (NPREG-1022)
E-Operator Training and License Examination. 5-Reduction F-Admini strative 9-Other 5
G-operational Error (Explain) Exhibit I-Same Source H-Other (Explain) w -- . . . _ _ . _ . - - ._ .