ML20090M765
| ML20090M765 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/29/1992 |
| From: | Hollomon T, Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9203250219 | |
| Download: ML20090M765 (10) | |
Text
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J L Wdson u m ne w.m ro w,s3N o w r w March 16. 1992 U.S. Nuclear Regulatory Conunission ATTN: Document Contrni Desk Washington, D.C. 20555 Gentlement In th( 'latter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PIANT (SQN) - FEBRUARY 1992 MONTHLY OPERATING REPORT Enclosed is the February '1992 Monthly Operating Report as required by SQN Tecanical Specification 6.9.1.10.
If you have any questions.ancerning this imitter, please call M. A. Cooper at (615) 843-8924.
Sincerely, 0
3 r%
/
L. Wilson Enclosure cc: See page 2 l
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U.S. Nuclear Regulatory Commiosion Page-2 March 16, 1992 cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 2085; Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 Palo Alto, California 94304
-NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379 Regional Administration U.S. Nuclear _ Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
Mr. B. A. Wilson, Project Chief.
U.S. Nitclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900
. Atlanta, Georgia 30323 Mr. F. Yost, Director Research Services Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006
.._, _. _. -. - ~
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4 1
TENNESSEE VALLEY-AUTHORITY NUCIEAR POWER GROUP SEQUO'.AH NUCl2AR PIANT i
MONTHLY OPERATING REPORT TO THE NUCIEAR REGUIAft)RY C0F9tISSION 5
FEBRUARL1932 i,
UNIT 1 DOCKET NtMBER 50-327 LICENSE NIMBER DPR-77 UNIT 2-DOCKET MIMBER 50-328 :
LICENSE NIMBER DPR-79 i
1 3:
i-1 w
OPERATIONAL
SUMMARY
FEBRUARY 1992 UNIT 1 Unit 1 generated 690,550 megawatthours (MWh) (gross) electrical power during February with a capacity factor of 85.38 percent. Unit I was operating at i
100 percent reactor power level on February 13 at 0113 Eastern standard time (EST), when a power level decrease to 70 percent power level was initiated to allow repair of the Number 3 heater drain tank Level Control Valve (LCV) LCV-6-10614 it appeared that the plug had separated from the stem. At 2348 (EST) on February 13, a further decrease in reactor power level was initiated as a result of chemistry requirements being exceeded on steam generator blow down because of a condenser tube leak.
On February 14 at 0222 (EST), Unit 1 power level reduction was tenninated at 30 percent reactor power.
On February 18 at 0026 (EST), a power level increase was initiated.
Unit I was operating at 100 percent reactor power level at 1635 (EST) on February 21.
On February 27 at 1725 (EST), Unit I reactor power level was decreased to approximately 82 percent to allow work on Number 7 heater drain tank LCV-6-109A.
On February 28 at 0812 (EST), an additional power level decrease to 80 percent was initiated to remove Condensate Booster Pump (CEFI 1A from service to repair a casing vent valve leak.
On February 28 at 2050 laS1),
reacter power level increase was initiated.
Unit 1 was operating at 100 percent reactor power on February 29 at 0400 (EST), and continued to operate at 100 percent through the end of February.
UNIL2 Unit 2 generated 628,470 MWh (gross) electrical power during February with a capacity factor of 77.71 percent. Unit 2 was operating at approximately 96 percent reactor power level at the beginning of February and was in coastdown to the Unit 2 Cycle 5 refueling outage.
On February 10 at 0528 (EST), with Unit 2 operating at 89 percent reactor power level, a reactor trip occurred-when the turbine tripped as a result of low auto stop oil pressure.
The unit had been operating with no abnormal indications before the trip.
-Unit 2 had received a reactor trip "P-9 Turbine Trip / Reactor Trip." The cause i
of the event was determined to be the failure of the autostop trip solenoid valve on the turbine trip block.
Unit 2 was returned critical at 1329 (EST) on February.11 and entered Mode 1 at 2015 (EST). Unit 2 tied online on February 12 at 0219 (EST). On February 19 at 1547 (EST), Unit 2 reactor power level was at 87 percent.
Unit 2 continued the coastdown to the Unit 2 Cycle 5 refueling outage.
Unit 2 4
was operating at approximately 79 percent reactor power level at the end of
?
February.
E0HER-O P ER.ATEILE6LIELVALVES_lEORYLANILS AFEILVAIXES.J UtlMARY There were no challenges to PORVs or safety valves in February.
V I
l
AVERACE IMILY UNIT POWER LEVEL l
DOCKET NO.
_5.0-31Z_
UNIT No. _ Que DATE: _03:05-92 COMPLETED BY: L_L_llollomon TELEPHONE:.(6.111_PA3-1528 MONTil - FIERL%RY_lR22 AVEPAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY QNe-Net)
DAY QNe:HeO 1
1149 17 271 2
11AS 18 622.
3 1148 19 730 4
1148 20 712 5
1148 21 1Q17 6
1147 22 1138 7
1147 23 1142 8
1147 24 1142 9
114L _
25 1131 10 1144 26 1141 11 1144 27 1101 12 1137 28 941 13 E25 29 Il40 14 303 30
...__R/t.15-283 31 N/A 16 2&7 i
L
- =. - -.
t AVERAGE DAILY UNIT POWER IR EL DOCKET NO.
._10-328 UNIT No.
Two DATE:
03-05-92 COMPLETED BY:
L_ JJiollomon TELEP110NE:
(_611LBh3-1328 MONTil: IIBRUARY 1992 AVERAGE DAILY POWER LEVEL AVERAGE JAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe:He.tl 1
10_82 17 93 5 2
1075 18
_26 1 3
1069 19 9.Z2 4
_106.0 20 91 6 5
1952 21 967 6
1045 22 935 7
103h_
23 946 8
102l 24 938 9
1Q19 25 933 10 217 26 928 11
-33 27 222 12 210 28 907 13 564 29
&98 14
-769 30 N/A 15 825 31 N/A l
16 919 l
OPERATING DAT A REPORT DOCKET NO.
_50-327 _ ___ _
DATE tiatub _j 99L._.
COMPLETED BY I wL_tiolf attiotL_
TELEPHONE (bihLS43-/$20.._
4 l
OfE!M11?G_11All)i lNotes l
1.
Unit Name: _JtWtty ttLUniL0nt_
l l
l l
2.
R= porting Period: libryar.yJ93L_
l l
Licensed Thermal Power (MWt): _3411A_._
l 3.
Hameplate Rating (Gross tMe): _122QJ.
l J141dL__ _
l 4.
l Design Electrical Rating (Net PMe):
JHLO l
S.
J Maximum Dependable Capacity (Gross HWe):
.l._
Give Reasons:
6.
ll2LO Hamimum Dependable Capacity (Net HWe)
If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since last Report, 7.
8.
__J/A Power Level lo Which Restricted, If Any (Not FMe):
9.
N/A
- 10. Reasons for Restrictions, if Any:
Cur..ul a t i v e This Month Yr.to-Date 1.440 _
93JQS
- 11. Hours in Reporting Period 69L______
.._40 J14 J_
1.44QtQ_
69ht0_
0
- 12. Number of Hours Reactor Was Critical 0 _
0 1.44010_.
$Lllld_..
- 13. Reactor Reserve Shutdown Hours
___ 196, L 0
- 14. Hours Generator On-line 00__
_15stisL910 0
- 15. Unit Reserve Shutdown Hours
_ L Q13 J 341 L 4.333 31LL
- 16. Gross Thermal Energy Generated (HWH)
_____flQJ5Q_
____LL65,1QB__
.__$2,232J84 _.
- 17. Gross Electrical Energy Generated (HWH)
_._66.1.739
_ 1.502J33___.
JLQ72.367
- 19. Unit Service Factor 10010_
l.00 D_
.- 501$_
- 18. Het Electrical Energy Generated (FMH) 10h0_.
SQd_
100.0_
93,3,.
_ dhZ__.
- 20. Unit Availability Factor 0_411 _
- 21. Unit Capacity Factor (Using HDC Net)
____91,2_
Abit,.
BLB 40.7 _
- 22. Unit Capacity Factor (Using DER Net)
QJ_
__ Q J_ _._._
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
25, if Shut Down At End Of Report Period, Estimated Date of Startup:
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.-... ~.-
. ~.-.
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1
+
l.
OPERATING DATA REPORT
]
DOCKET NO. _$0-RfL DATE _titti_h 139L.__
COMPLETED BY T. J. Hollpect._
TELEPHONE 16HLSA3-1528_
OfLRAIIHL11AlUi l Notes l
1.
Unit Name:
.$tgugyah.Un1Llwo l
l 2,
Reporting Period: _Lebruary 1992 l
l 3.
Licensed Thermal Power (HWt): _3AILO l
l 4.
Nameplate Rating (Gross HWe): 1220.6 l
l 5.
Design Electrical Rating (Net FMe): _ll4_0J l
l l
6.
Maximum Depomlable Capacity (Gross HWe): _1.lfLO l
l
- 7.. Maximum Dependable Capacity (Net HWe): _1.12LO l
l 8.
if Changes Occur in Capacity Ratings (! tem Numbers 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted. If Any (Net NWe):
- N/A 10 Reasons for Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 6S6 1.fd0 85,%$
- 12. Number of Hours Reactor Was Critical 664.0 1.40LD_
- 50. 416___ _.
- 13. Reactor Reserve Shutdown Hours L
0 0
- 14. Hours Generator On-Line 651 2 _
1 395,2_
49, A3ha_,
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross Thermal Energy Generated (HWH).
1.84 L % 313_ _
..... 4.367.65Z 4._
_15L294.970
. 17, Gross Electrical Energy Generated (HWH) 628.470 ____
1.491.15L_ - _5L649.447
- 18. Net Electrical Energy Generated (HW11)
-603.339' 1.436.861 50381.825
- 19. Unit _ Service factor 93.6 96.9 57.8
- 20. Unit Availability Factor 93.6 9Q 57.8_,
- 21. Unit Capacity' Factor (Using HDC Net) 77.3 BM 52.5 _
- 22. Unit Capacity Factor (Using DER Net) 75.5 86.9 S l d._,
i
- 23. Unit Forced Outage Rate 6.4 3.1 35,A_
' 24. Shutdowns Scheduled Over Hext 6 Honths (Type. Date, and Duration of Each):
Unit 2 Cvele 5 refuelina outage is ssheduled to begittiarsh-13. 1902.' and is a rrentiv scheduled as a 65-day _gutage.
!=
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
N/A P
l' k
I l
y h.
7:
~
m m
l DOCKET NO:
50- m UNIT SHUTDOWNS #4D POWER REDUCTICNS UNIT NAME:
One DATE:
03/10/92 s-REPORT HONTH:_ Lebruary 1991-
' COMPLETED BY:T. J Hollomun TELEPHONE:(615) 843-75Z8 Nethod of Li ct-nsee Cause and Correctivr r
Duration Shutting Dow Event Syste Code,m Compgnent' Action to
[
No.
Date Type (Hours)
Reason' Reactor Report No.
Code Prevent Recurrence t
1 2/13/92 1
N/A-'
A/B 5
'l N/A N/A N/A 09 2/13/92 at 0113 (EST), a power level reduction to 70 percent was initiated to allcw repair of the Nurber 3 heater drain tank level control valve (LCV) LCV-6-105B.
It appeared the plug had separated.
i Corrective maintenance was performed on LCV-6-1068 and the valve was returned to service. At 2348 (EST) on 2/13/92, a further i
decrease to 30 percent reactor v
power level was initiated as a.
result of chemistry requirements being exceeded on steam generator blowdown because of a condenser-tube leak. The condenser tube leak was corrected. On 2/18/92-i at 0526 (EST), reactor power i
increase was initiated.
5 2
2/27/92 1
N/A B
5 N/A N/A N/A On 2/27/92 at 1725 (EST), reactor power level was reduced to 82 percent to perform corrective I
mai9tenance on No. 7 heater drain i
I tank LCV-6-109A. On 2/28/92, an additional decrease to 80 percent
{
was initiated to repair a casing i
vent valve leak on the lA condensate booster pump. At 2055 (EST) on 2/28/92, reactor power level increase was initiated.
Y :' forced 2
3 kxhibit G-Instructions F
Reason:
Method:
5: Scheduled A-Equipment failure (Explain) 1-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
( NUREG-1022)
E-Operator Training and License Examination 5-Reduction i
F-Administrative 9-Other 5
G-Operational Error (Explain)
Exhibit I-Same Source r
H-Other (Explair) r
=
~
DOCKET tt0:
'50-373
^
UNIT SW TDOWNS AND POWER REDUCTIONS
'tMIT NAME:
he DATE:
03/10/92-REPORT MONTH: February 1992 COMPLETED BY:T. J. Nollonen TE1.EPHONE:f 6151 8a3-7*2B -
Method of.
Licensee Cause and Corrective '
Duration Shutting Down Event System Component Action to l
2 3
ll No.
Date Type (Hours)
Reason Reactor Report No.
Code #
' Codes Prevent Recurrence Unit 2 was in coastdown to U2C5 refueling outage at the beginning of February.
1
'2/10/92.
F 44.9 A
3 328/92001 TG PSV On 2/10/92 at 0528 (EST), Unit 2 reactor tripped when the turbine tripped as a result of low auto stop oil r essure.. The cause of the event was the failure of the autostop trip solenoid valve on the turbine. trip block.
Unit 2 was online again on 2/12/92 at 0219 (EST) and began increasing power. Unit 2 reached approxi--
mately 87 percent reactor power on 2/19/92 at 1547 (EST), and resumed coastdown to U2C5 refueling outage.
4 k
i
?
r i
j I: Forced Reason:
Hethod:
Exhibit G-Instructions 2
3 F
5: Scheduled
.A-Equipment Failure (Esplain) 1-Manual for Preparation of Data
[
- B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee j
'C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction e
F-Administrative 9-Other
-f G-Operational Error (Explain)
Exhibit I-Same Source f
5 H-Other (Explain) :
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