ML20116M406
| ML20116M406 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/1992 |
| From: | Hollomon T, Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9211200256 | |
| Download: ML20116M406 (10) | |
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renasce veiev -a, ty. est ofre oc, zyx) socay.owsy vn,wsse, 37379 J L. Mson wa em#ni sem,a8 tuw cura November 16, 1992 U.S. Nuclear Regulatory Commission i
ATTN:
Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
)
Docket Nos.30-327 Tennessee Valley Authority
)
.50-328 SEQUOYAll NUCLEAR PLANT (SQN) - OCTOBER 1992 MONTHLY OPERATING REPORT Enclosed is the October 1492 Monthly Operating Report as required by SQN Technical. Specification 6.9.1.10.
If you have any questions concerning this matter, please call M. A. Cooper at (615) 843-8924.
Sincerely,
?
S /W.,
/
{
L. Wilson
. Enclosure cc: See page 2 200025
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U.S.-Nuclear Regulatery Commission Page 2 November 16, 1992 cc (Enclosure)
INPO Records-Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339-3064 Mr. D. E. LsBarge, Project Manager U.S. Nuclear Regulatory Commission One White. Flint, North 11555 Rockville Pike Rockville Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412
'T Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant
-2600 Igou Ferry Road Soddy-Daisy, Tennessee'37379-3624
_ Regional-Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, F", Suite 2900 Atlanta, Georgia 30323-2711 Mr. B.LA. Wilson, Project Chief
~U.S Nuclear Regulatory Commission
-Region II 101 Marietta Street,PAJ, Suite 2900 Atlanta, Georgia 30323-0199-l-
Mr. P. Yost, Director Research Services Utility Data Institute.
1700 K Street.-NW, Suite 400-
-Washington, D.C. 20006-3800 f
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TENNESSEE VALLE" AUT11bRITY NUCLEAR POWER TiWP.
SEQUOYAH NUCLEAR FIANT MNTHLY OPERATING REPORT
'R) THE NUCLEAR REGUIATORY C0fftISSIM -
QCIDBER 1999, UNIT 1 DOCKET NUMBER 50-327 1
LICENSE NINBER DPR-77 UNIT 2 DOCKET NIMBER 50-328 LICENSE NUKBER DPR-79--
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OPERATIONAL
SUMMARY
OCTOBER 1992-ITNII_1 Unit 1 generated-723,030 megawatthours (MWh) (gross) electrical power during October with a capacity factor of 83.52 percent.
Unit 1 operated at near 100 percent reactor power until October 26.
On October 26, 1992, at 1855 Eastern standard time (EST), the reactor tripped because of a turbine trip that resulted from a high-high feedwater level in i
the No. 3 steam generator.
Before the trip, water was inadvertently introduced h.to the control air system, inducing. secondary plant transients that resulte6 in a turbine runback to 81 percent.
Before the Unit 1 turbine-runback, steam generator No. 3 was experiencing low level as a result of water intrusion in the pneumatic positioner at the feedwater regulating valve (FRV). The unit ope,utor placed the flow indicating controller (FIC) in maaual for 'he steam generator Nv. 3 FRV to attempt to gradually raire the level. The automatic-manual switching relay (K-1) for this FIC did not change state, causing the manual control circuit to be electrically inoperable. This condition resulted in the FRV going to the full open position and not responding to the controller in automatic or manual. Attempts to close the valve were unsuccessful, resulting in a high-high level turbine trip.
Unit I remained in Mode 3 at the end of October while recovery actions for the control air water intrusion continued; the K-1 relay in 1-FIC-3-90 was replaced.
UNIT-2 Unit 2 generated 765,510 MWh (gross) electrical power during October with a capacity factor of 88.54 percent. Unit 2 operated at near 100 percent rear-power until October 26.
On October 26, at 1855 EST, Unit 2 experienced a runback to 67 percent power when introduction of water into the No. 3 heater drain tank level controllers (by the event dese;ibed above) resnited in feedwater bypass to the condenser.
Power _ ' further reduced until'the unit was stabilized at approximately 55 percent power.
3 On October 27, at 0645 EST, intermediate Heater String C isolated.- At 06h9 EST, intermediate Heater String B isolated, and a reactor power reduction to 30 percent was initiated. At 0710 EST, Unit 2 was stabilized at 30 percent reactor power.
Unit 2 remained at 30 percent-reactor power at the er.d-of October while recovery actions for the control air water intrusion continued.
-l 1
EDWER-GEERAIED_RELIEE_YAIXES _(PARVxl_AND_SAEETE_ VALVES SUhMARY There were no challenges to PORVs or safety valves in October.
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1 AVERAGE DAILY UNIT POWER IFIEL D')CKET NC.
_.Q-121 UNIT No. _ Qae DATE: ' J 1_Q4-91 COMPLETED BY:
I. J. Hollonion TELEPHONE:..(115 _8A3-2ji28 MONTil:
QCIQBER_l9.9L AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWa-Het)
DAY (MWe-Ng t.l_,
1 11.27 17 113L 2
1120 18
_1132 3
1128 19 1133 4
1130 20 1136 5
1129 21 1137 6
1129 22 1135 7
1126 23 1139 8
1129 24 1132 9
1127 25 1140 10 1128___.
26 891 11
29 47
-26 12 1128 28
-25 13 1129 29
-23 14 1130 30
-22 15 1130 31
-23 16 llL
-l
i AVERACE IMILY IMIT POWrR LEVEL DOCKET NO.
__10-328 UNIT No. __Ixo Dt.TE : - _11-06-92 COMPLETED BYt T uTuPollomon TE',EPHOIJE: 1115) 843-Z528 MONTII: OCIDB.ER_129.2._
AV 'E 3JE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY
.IMWe-He.O_
DAY (MWe-Net.l__
1
._._ __ _ _1125 17 1129 2
.__1174 18 1130 3
112_4 19 1131 4
1125 20 1131_,.
l 5
1176 21 1132 l
6 1126 22 1133 7
1125 23 113-2 8
1125 24 1133 l
l 9
1124 25 1131 10 1125 26 1033 11 1175 27 402 i
12 ll26 28 295 13 112E 29 195 i
14 112fi 30 295 l-15 1i23 31
__293 16
_1128
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.-2 OPERATING DATA REPORT DOCKET NO. 1.50-311_-
DATE._11/Q6/91_.
COMPLETED BY
- 1..L Hollistort_
TELEFi10NE (6El 8%2520__
_DEEEA11EG_11&lDS l Notes
]
1.
Unit hame: __11Runyah Unit One l
l 2.
Reporting Period: Qttnber 1992 l
l 3.
Licensed Thermal Power (HWt): _341).0 l
l Nam plate Rating (Gross Hve): _1[RD.6 l~
l 5.
Design Electrical Rating _(Net HWe): 1148.0 l
l 6.
Maximum Dependable Capacity (Gross HWe): 1162.0 l
l 7.
Maximum Dependable Capacity (Net HWe): _1122.0 l__
l 8.
If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report Give Reasonst-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 745 7,iED. __
.__.__99.385
- 12. Number of Hours Reactor Was Critical 619.9 6.357.5_
53.311
-13. Reactor Reserve Shutdown Hours 0
-0
-0
- 14. Hours Generator On-Line-619.9 6.313.d_;_
_52.!G4.5
- 15. Unit Reserve Shutdown Hours 0.0 O
0
- 16. Gross thermal Energy Generated (HWH) 2.107.322.4 20.790.54525_
170.403.078
- 17. Grnss Electrical Energy Generated (HWH) 723.030 7.080.198 57.747.694
- 10. Net Electrical Energy Generated (HWH) 696.041 6.816.307 55.381.041
- 19. Unit Stevice Factor 83.2 E61Z_
52.5
- 20. Unit. Availability factor
_JB3.2 86.2 52.5
- 21. Unit Capacity Factor (Using tDC Net) 83.3 83.0 49.7,,
- 22. Unit Capacity Factor (Using DER Net) 81.4 81.1 48.q__
- 23. Unit forced Outage Rate 16 8 13.8 39.1 2
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
Tue Cvgle_1rt19qlinLoylage is scheduled to bgain on April 2.1993. with a durat. ion or 65
.dgJA.
- 25. If Shut Down At End Of Report Period, Estimated Dat( of Startup: _Roytsher_2'. If92 l
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OPERATING DATA REPORT DOCKET NJ, _11-328 DATE _11/16/97 COMPLETED BY L_.h Hollomun__
TELEPHONE (615) 843-23J L OfLRAllNLilAlll5 lHotes l.
1.
Unit Name: __$tguayRh_Ilall.IF12.
l l
2.
Reporting Period: _Qtinher_1992 l
l 3.
Licensed Thermal Power (HWt): _19112Q.
l l
4.
Nameplate Rating (Gross HWe): _122A16 l
-l 5.
Design Electrical Rating (Net HWe): _1138,0 l
l 6.
Maximum Dependable Capscity (Gross HWe): _1162.0 l
l 7.
Hanimum Dependable Capacity (Net NWe): 1122.0 I
I 8.
If Changes Occur in Capacity Ratings (Item Numbers *
.ough 7) Since Last Report, Give Reasons:
9.
Po-er Level To Which Restricted, If Any (Net HWe).
___HIA.
- 10. Reasons For Restrictions, If Any:
N/A This Month Yr-to-Date
' Cum; 9 a tive
- 11. Hours in Reporting Period 745 7.320 91.345
- 12. Number of Hours Reactor Was Critical 74E.0 5 14Etl.
54.751 13.- Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 745.0 5.572.4.
33,311,$__
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross Thermal Energy Generated (HWH) 2.255.338.0
. 17.413 182ms.
168.341.303 2
- 17. Gross Electrical Energy Generated (HWH)
___16E 510 5.903.043 57.061.334
- 10. Net Electrical Energy Generated (HWH) 737.484 5.665,214 54.610.178 i
- 19. Unit Service Factor 1 ED.,0 JJEul_
58.7
- 20. !Jnit' Availability factor 100.0 76.l_
58.7
- 21. Unit Capacity Factor (Using HDC Net; 88.2 69.0-53.3
- 22. Unit Capac!ty Factor (Using DER Net)
_H622___
67.4 52.1
-23. Unit Forced Outage Rate 0.0
- d,4_
33.7 24; Shutdowns' Scheduled Over N2xt 6 Honths (Type. Date, and Duration of_lach):
- 25. If Saut Down At End Of Report Period. Estimated Date of Startup:
w DOCKET NO:
50-329 UhIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
Twq a
DATE:
11/09L22___
REPORT MONTH:. OCTC6LR 1997 COMPtETED BY:T,_l,_H 110stn 2
TELEPM)NE:(615) 843-75Z3 Cause and Corrective l Licensee Systgm Compgnent Methcd of Event Action to Duration Shutting,Down No.
Date Type (Hours)
Reason Reacter" Report No.
Code Code' Prevent Recurrence
- .t 1854 Eastern stand rd time.
8 921026 F
A 5
Unit 2 had a runback as a result of water intrusion into the No. 3 heater drain tank lev.1 con-
' roll e rs.
The cause vi the water
.intrusion into the station control air system was condensate accumu-lation in the No. 2 receiver tank due to sediment buildup in the bottom of the tank. This prevented the traps and shif tly ennual blow-cewn through the bypass drain from being effective. Af ter identi-fying that water intrusion into the control air system had occurred, an action plan was developed and implemented to correct the condi-tion. hier was removed from the system by blowing down the system while venting and draining the system until the system air qual-ity was determined to be accept-able.
2 Method:
Exh>;it G-Instructions 3
I: Forced Reason:
F 5: Scheduled A-Equipnent failure (Explai,)
1-Manual far Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee l
C-Refueling 3-Automatic Scram Event " sport (LER) File 4-Continuation of Existing Outage (NURCG-1022)
D-Regulatory Restruction E-Operator Training and License Examination 5-Reduction F-Admi ni s t ra.i ve 9-Other SExhibit I-Same Source G-Operational Error (Explain)
H-Other (Explain)
DCCKET NO:
50-22O _
UNIT SHUTDOWNS AND POWER REDUCT13NS UNIT NAME:
One
'OATE:
11/09/92 REPORT MONTH: OCTOBER 1992 COMPLETED BY:T. J. Hollomon -
TELEPHONE:(6151 843-7528- ;
f Method of Licensee Cause and Corrective Du ration Shutting,Down Event System Compgnent Action to I
2 D
No.
Date Type (hours)
Reason Reactor #
' Report No.
Code Code Prevent Recurrence 8
921026 1
125.1 A
3 50-327/
003 RLY The reactor trip was precipitated 92018 by a turbine trip. The turbine l-tripped as a result of high-high feedwater level in the No. 3 steam generator, resulting from the.
failure of the loop No. 3 FRV.
i The controller malfunction was caused by the automatic-manual i
switching relay (K-1) failing to change states. This resulted in the valve going to the full open position when the operator went from automatic to manual control.
Prior to this event, water was introduced to the nonessential control air system, resulting in secondary plant transients. The K-1 relay was replaced, and the valve was 2. turned to operable status. Water was iemoved f rom the systed by blowing down the system while venting and draining the system until the system air quality was determined to be acceptable.
4 a
I :-Forced
.2 3
F Reason.
Hethod:
Exhibit G-Instruc.lons 5: Scheduled A-Equipment failure (Explein) 1-Manual for Preparation of Data B-Naintenance 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 Lic*nse Examination 5-Reductioa F-Admini strati ve 9-Cther.
5 G-Operational Error (Explain)
Exhibit I-Same_ Source H-Other (Explain).
_ _ -