ML20105C170
| ML20105C170 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1992 |
| From: | Holloman T, Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9209220124 | |
| Download: ML20105C170 (12) | |
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September 15, 1992 U.S. Nuclear Regulatory Conunission l
AT171 Document Control Desk i
Washington, D.C. 20555 f
Gentlemen:
s In the Matter of
)
Docket Nos. 50-327 f
Tennessee Valley Authority
)
50-328 i
SEQUOYAH NUCLEAR PIANT (SQN) - AUGUST 1992 MONTHLY OPERATING REPORT Enclosed is the August 1992 Monthly Operat!ng Report as required by SQN Technical Specification 6.9.1.10.
If you have any questions concerning this matter, please call J. D. Smith at (615) 843-6672.
i Sincerely, j'
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L WL JI 1,. Wilson Enclosure cc:
See page 2 9
9209220124 920031 V
DR ADOCK 05000327 j,h -
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l U.S. Nuclear Regulatory Commission j
Page 2
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September 15, 1992 l
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cc (Enclosure):
1 INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 l
Mr. D. E. 1.aBarge, Project Manager j
l U.S. Nuclear Regulatory Commission l
One White Flint, North 4
11555 Rockville Pike l
Rockville, Maryland 20852 I
j Mr. Ted Marston, Director Electrie 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 i
Regional Administration.
}
U.S. Nuclear Regulatory Commission office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323
}
Mr. B. A. Wilson, Project Chief U.S. Nuclear 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,IN, Suite 400 Washington, D.C. 20006
_ _.._. -._. ~. _ _ _ _ _. _ _ - _. _ _.. -._... -. _ _ _ _. -. _.._ _ _. _ _ _ _ _ _ _._ ____._ _ _ _ _
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TENNESSEE VALIEY AUTil0RITY i
NUCLFAR P(MER GROUP SEQUOYAll NUClfAR PLANT
?10NTilLY OPERATING REPORT TO TIIE NUCIEAR REGUI.ATORY C0ft11SSION AUGUSL1992 UNIT 1 DOCKET NUttBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE nut 1BER DPR-79
1 OPERATIONAL
SUMMARY
AUGUST 1992 VNITJ l
I l
Unit i generated 837,900 tnegawatthours (MWh) (groad) electrical power during August with a capacity factor of 96.92 percent.
i f
On August 4, 1992, at 0959 Eastern daylight time (EDT), Oncrations and Maintenance personnel were attempting to isolate the electrohydraulic controller oil to each pair of intercept and reheat valves on the snoisture separator reheater (MSR) to identify individual servo valves with excessive l
l 1eakage and to potentially correct a cycling problem.
During the
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troubleshooting process, both flow paths from the "A" MSRs to the low pressure l
tutbine "A" were inadvertently isolated simultaneously. The resulting high l
pressure in the remaining MSRs caused the lifting of several safety valves.
The operators immediately opened the isolated intercept and reheat valves.
This transient resulted in a turbine runback to 75 percent power initiated by a high-level bypass of the No. 3 heater drain tank (llDT).
Following the
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runback, the plant was stabilized at 72 percent power at 1010 EDT.
}
i Aiter a thorough investigation into the cause of the event and any possible j
damage to the turbine, the MSRs, and the feedwater beaters, the plant was j
returned to f ull power.
Unit I was again at 100 percent reactor power on i
August 5 at 0127 EDT.
l l
I Unit i reactor power level was decreased again on August 16 at 0423 EDT when the "fi" No. 3 IIDT oil reservoir was f ound overflowing. Power level decreacc was terminated at 84 percent power at 0623 EDT. At 1050 EDT, repairs were complete, and a power level increase was initiated.
Unit I was again at 100 percent reactor power level on August 16 at 1415 EDT.
Unit 1 operated at near 100 percent reactor power through the end of August.
I UNII_2 Unit 2 gene.ated 732,391 MWh (gross) electrical power during August, with e capacity factor of 84.72 percent.
j i'
on August 21, 1992, with Unit 2 operating at approximately 100 percent power, reactor trip occurred at approximately 1321 EDT when a spurious signal, a
generated on all four pressurizer pressure channels, initiated a low pressurizer pressure trip signal and two of three channels generated an automatic safety-injection signal. Unit 2 entered Mode 3.
An investigation.
revealed the most probable cause to be an inadvertent radio transmission in i
the seal table area.
I i
Unit 2 was again critical on August 22 at 2207-EDT,. entered Mode 1 on
.[
August 23 at 0455 EDT, and tied online at 0732 EDT that day.
On August 24 at 1540 EDT, Unit 2 was at 68 percent power level and holding for repair work on j
the 2B condensate booster pump injection water differential pressure switch.
l At 1738 EDT that day, repairs and postmaintenance testing were complete, and a j
power level increase was initiated.
Unit 2 reached 100 percent power at 0530 l
EDT on August 25.
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Unit 2 reactor power level was decrenned from 100 percent to 56 percent on j
j Auguct 27 to perf orm raaintenance on both main f eedwater pumps. The power level decrease was initiated at 1824 EDT and terminated at 2221 EDT. On l
l August 29 at 1522 EDT, repairs were completed and controls were in automatic.
j Unit 2 was available for 100 percent power, but at the request of load j
control, remained at 60 percent reactor power.
l on August 31 at 0400 EDT, Unit 2 power level increase was initlated. At 0635 i
j EDT. the 2B condensate demineralizer booster pump (CDBP) failed to start t
}
according to procedure.
Reactor power level was increased tc, 80 percent and f
j held until problems with the 2B CDBP were resolved. At 1745 EDT, reactor j
j power level increase wes resumed, and Unit 2 was at approximately 90 percent i
j reactor power level at the end of August.
l l
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l I'DWER-REPMED_RElJEF_VAIMES_II'ORVa)ED SAFEILVALVEH.3M1AM I
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There were no challenges to PORVs or safety valves in August.
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t AVERACE 11AILY 11 NIT POWER LEVEL l
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i DOCKET NO.
_ 10-327.
TWIT No. _ One_ _.
DATE:
09-08-92..____
COMPLETED BY:
T,_. J,_Ilollomon TELEP110NE: Ih11)_Bl3-Z123 i
MONiil: AUGUSL1992_
AVEPAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL 1%Y (We:NeO IMY IWerNed I
_.._ _ _ _103z 17 1093 j
2
_ 1028 18
.3097 3
1997 19
_1017 4
9h0 20 1016_
S
_._ ___108 L 21 (Q93 l
6
_.._ ___ _ l093 22 1098_
7 1Q95 23 1100 8
10Sb 24 JL49 9
.109L_ _
25 1101 10 1996 26 1103 11 1016 27 110.2 12 1016 28 1109 13 1093 29 1100 14 1 995 30 1101 15 101L 31 1098 16 J029
AVERACE DAILY UNIT POWI:R IJNEL I
l DOCKET NO.
,JS 32E_
UNIT No. __Two DATE:
_Q2-QS-22_____
l COMPLETED BY:
Ta_1_llollemen TELEPHONE:
1615)_843-Z528 j
MONTH: AUGUEL199L j
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i AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL
[
TwY (MWe-Re.t)
DAY (t1Re-NeD j
1
-_.__ __ _.1103 17 1101 2
1103 18
.1106 3
L102_
19
-11Q6 4
._____ ___1103 20
_1105.
f 5
_1104 21 62Z._
6 1103_
22
-19 7
J104 23 92 i
i 8
1105 24 610 9
1105 25 1Q91
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10 1105 26
..[101 i
11 1104 27 1Q35 i
12
_1109 28
.635 f
13 1109 29 614 I
I 14 ILQ9 30 61B 15 110L 31 71 1 16
__ ___ _l103 I
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OPERATING DATA REPORT l
1 DOCKET NO.
_$0-321 DATE 09/OS/R COMPLETED BY L_h Jol]M2a_
TELEPHONE 161 HLB 43-7528 QELRAll!G_$IALUS l Notes l
1.
Unit Name: __Stqvny thA LLOM
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2.
Reporting Period: AsgnL1922 l
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3.
Licensed Thermal Pnwer (HWt); _3411d___
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l 4.
Nameplate Rating (Gross MWe): _122L6 l
l 5.
Design Electrical Rating (Net HWe): lldhD l
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l 6.
Maximum Dependable Capacity (Gross HWe):,_llhh0__
l l
7.
Haximum Dependable Capacity (Net HWe): _1.112,0 L
l 8.
If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since last Retort Give Reasons:
j j
i 9.
Power level To Which Restricted, If Any (Net HWe): __J4/A f
- 10. Reasons for Restrictions, if Any:
__N/A i
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Feriod 7_44 L B 55_ __
9L9/0
- 12. Number of Hours Reactor Was Critical 744tQ
._5JJJJ_
Sb971 f
- 13..~.eactor Reserve Shutdown Hours 0
0 0
i
- 14. Hours Generator On-Line
_ _144,9__.
$,9].Jd_
5Q,044.6
- 15. Urit Reserve Shutdown Hours
_310 Q_
O__._.
- 16. Gross Thermal Energy Generated (tMI)
_ L511&204L_
16.239.149 L JhhBi1ML_
1
- 17. Gross Electrical Energy Generated (HWH) 83L909____
__5J30JhB__..
__hbl91&4 lb. Net Flectrical Energy Generated (HWH)
_018J11__
,__5J2h510_
___5LB E 244
- 19. Unit Service Factor 100J 84_J_
51.9
- 20. Unit eval 1 ability factor 10L 0____
34A 51.9
- 21. Unit Capacity Factor (Using HDC Net) 969_
81.0.
49.0
- 22. Unit Capacity factor (Using DER Net) 962 79.L 47.9
- 23. Unit forced Outage Rate 0. n.
15.1 39.7
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
- 25. If Shut Dawn At End Of Report Period. Estimated Date of Startup:
__-~---.--,
I OPERATING DATA REPORT DOCKET NO. J0-378 DATE _03/08/92 COMPLETED BY L_h_t!Q119tnon.L_
l TELEPHONE 1615) B & Z52!L.
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OrLRABM_SIMUS
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l Notes l
1.
Unit Name: _ltguonh Unillwo l
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2.
Reporting Period: _Augus1 1922__
l l
g 3.
Licensed thermal Power (HWt):._3!1 60 l
l
[
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4, Hameplate Rating > (Gross HWe): 122L.6 l
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4 5.
Design Electrical Rating (Net HWe): 114LO l
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i 6.
Maximum Dependable Capacity (Gross HWe): _1.HL O l
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7.
Maximum Dependable Capacity (Net HWe): _L12ZJL I
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0, if Changes Occur in Capacity Ratings (! tem Numbers 3 Through 7) Since Last Report. Give Reasons:
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9.
Power Level To Wnich Restricted, If Any (Net HWe):
_ULA j
i I f). Reasons for Restrictions, If Any:
fl/A I
}
Thls Month Yr-to-Date Cteulative f
I l
- 11. Hours in Reporting Feriod 144 _ _
5.655
_ _ SLBSIL.__
[
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- 12. Number of Hou's Reactor Was Critical 7)L Z__.
4 277.7 SLZQ6 i
- 13. Reactor Reserve Shutdown Hours 0
0 0
)
- 14. Hours Generator On-Line
____ __7DLB.__
4 1BL L
_ 5LZ3LJ__
i 2
l
- 15. Unit Reserve Shutdown Hours 0,D _
Q_
0 l
- 16. Gross Thermal Energy Generated (HWH) 2,177dBLb__
13.051,2S3J
_163J7L197 i
j
- 17. Gross Electrical Energy Generated (Ni) 71L331 4.420.773
_15.11LQ64 I
- 18. Net Electrical Energy Genera *.ed (HWH)
_ _ 7DL231 4 229.119 _ _ _33,1S3 483
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l
- 19. Unit Service Factor 94_i3.__
71 1 58.1
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1
- 20. LMit Availability Factor
$3_
71.5
$8.1
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- 21. Unit Capacity Factor (Using HDC Net)
_6L4_ __.
64 1_
SLl_
j 1
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- 22. Unit Captcity f' actor (Using DER Net) 8L3___
63.1 51 5_
(
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- 23. Unit forced Outage Rate 5 L__
2 6_
3 4., 3_
I
- 24. Shutdowns Scheduled Over Nest 6 Months (Type Date, and Duration of Each):
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- 25. -If Shut Down At End Of Report Period,- Estimated Date of Startup:
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00CxFT NO:._ 50-327 l
UNIT SHUTDOW15 MAD POWER REDUCTIONS UNIT NAME:
One i
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j-DATE:__22I22/2Z_,,
REPORT MONTH:_A.UM!ST 1992 _
COPptETED BY:TJ _tiqllpman TELEPHONE:(615) 8?3-7529 i
3 I
Method of Licensee Cause and Corrective l
[
]
Duration Shuttir.g Down Event System Component Action to l
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3 5
No.
Date Type (Hours)
Reason Reactor Report No.
Code #
Code Prevent Recurr--oce
+
~
l 7
920804 F
G 5
At 0959 Eastern daylight time (EDT), Operations and Maintenance personnel were attempting to j
isolate the electrohydraulic j
control oil to each pair of inter-cept and reheat valves on the j
moisture separator reheater (MSR) to identify individual servo
+
valves with excessive leakage and to potentially currect a cycling I
problem. During the trouble-I i:
shooting process, both flow paths
(
from the "A" MSRs to the low I
a I
pressure turbine "A" were inadver-tently isolated simultaneously.
}
The resulting high pressure in the j
4 remaining MSRs caused be li f ting I
of several safety valves. The t
l operators irunediately opened the
{
isolated intercept and reheat j
4 valves. This transient resulted in a turbine runback to 75 percent 4
power as a result of a high-level bypass of the No. 3 heater drain i
tank. Frilowing the runback, the i
plant was stabilized at 72 percent f
power at 1010 EDT. Unit I was L
again at 100 percent power on l
l August 5, 1992, at 0127 EDT.
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j I ; Forced 2
3 5
F Reason:
Method:
Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l
B-Maintenance or Test 2-Manual Scram Cntry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File I
D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022) i E-Operator Training ano License Examination 5-Reduction F-Administrative 9-Ot.ur 2
j G-Operational Error (Explain)
Exhibit I-Sr.me Scurce H-Other (Explain)
,-,m,.m_
DOCKET NO:
50-328 h
UNIT SHUTOCWNS AN POWER RED'JCTIONS t#4IT NAME:
TC DATE:
09/05/32 __
j REPORT t*0 NTH:__AyrgST 1992 COMPT.ETED TsV:T.1 Hql]1_qmon TELEPHONE:iS151 843-752*
4 l
l Method of Licensee Cause and Ccrrective I
I Duration i Shutting Down Event System Component.
Action to 4
i 1
2 1
4 5
I No.
Date Type (Hours)
Masen Reactcc Report No.
Code Code Prevent Recurrence 5
920821 F
42.2 G
3 A reactor trip occurred at approzi-mately 1321 EDT when a spuriois
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signal, ganerated on all f our t
i pressurizer pressure channels, ici-
[
tiated a low pressurizer pressure t
trip signal and two cf three chan-l nels generated an automatic safety injection signal. Unit 2 entered Mode 3.
An investigat.on revealed
[
the most probable cause to be an i
inadvertent radio transmission in I
j the seal t:ble area. Unit 2 was l
aoain critical on Augutt 22 at 2207 EDT: entered Mode 1 on August 23 at 045E EDT; and tied l
online at 0732 EDT that day. On August 24 at 1540 EDT. Unit 2 was i
at 68 percent power level and L
holding for repair work on the j
2B condens.te booster pump g
j.
injection water differential pre sure switch. At 1738 EDT that day, repairs and postmaintenance testing were complete and a power i
level increase was ir.itiated.
j.
Unit 2 reached 100 percent power at d
0530 EDT on August 25. 1992.
t 920827 F
B 5
Reactor power level was decreased i
from 100 percent to 56 percent to perform maintenance on both MFPs,
)
A power level decrease was ini-
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i tiated at 1824 EDT and terminated at 2221 EDT. On August 29 it l
1522 EDT, repairs were coirpleted l
(Con _tinued on_next_page) l 1
2 3
4 F: Forced Deason:
Method:
Eshibit G-Instructions l
5: Scheduled A-Equipment failure (Explain)-
1-Manual for preparation of Data j
B-Maintenance or Test 2 Nanual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scras Ever.t Report (LER) File f
l D-Regulatory Restruction
~ 4-Continuation of Ed sting Outage (NUREG-1022)
{
E-Operater Training and 1.icense Examination 5-Reduction f
F-Administrative 9-Other i
i 5
G-Operational Error (Explain)
Exhibit I-Same Source l
H-Other (Explain)
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