ML20128M940
| ML20128M940 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/31/1993 |
| From: | Fenech R, Hollomon T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9302220402 | |
| Download: ML20128M940 (10) | |
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Tennewee V@ey A#enty. Ftist Off ce Doe XXO Sxtty Da sr Tennessee 37379 2C(0 Robert A Fenoch r
v.cc moen, sewyan naa, nant February 16. 1993 1
U.S. Nuclear Regulatory Commission ATTN Document Control Desk l
Washington, D.C. 20$55 Gentlemen i
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 t
SEQUOYAH NUCLEAR PIANT (SQN) - JANUARY 1993 MONTHLY OPERATING REPORT Enclosed is the January 1993 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.
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Robert A. Fenech Enclosure f
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93022"dO402.930131 I
PDR -ADOCK 05000327
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U.S. Nuclear Regulatory Commission i
Page 2 February 16, 1993 cc (Enclosure):
INPO Records Center 4
i Institute of Nuclear Power Operations J
1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339-3064 i
Mr. D. E. LaBarge, Project Manager U.S.-Nuclear Regulatory Commission One White Flint, North
)
11555 Rockville Pike 1
Rockville, Maryland 20852-2739 i
Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412' 1
Palo Alto, California 94304 t
NRC Resident Inspector Sequoyah Nuclear Plant a
2600 Igou Ferry Road Soddy-Daisy, Tennessec 37379-3624 Regional Administration i
U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199 Mr. F. Yost, Director Research Services Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006-3800 t
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s TENNESSKE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOYAH NUCLEAR PIANT i
1 MONTHLY OPERATING REPORT
'tV THE i
I NUCLEAR REGULATORY COPMISSION 1
JANUARL1993 i
UNIT 1 1
DOCKET NUMBER 50-327 i
LICENSE NUMBER DPR-77 J
l UNIT 2
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DOCKET NUMBER 50-328
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LICENSE NIMBER DPR-79
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OPERATIONAL
SUMMARY
JANUARY 1993
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11 NIL 1 1
t Unit 1 generated 762,990 megawatthours (MWh) (gross) electrical power during a
January with a capacity factor of 88.26 percent.
I Unit 1 was in Mode 3 at the beginning of January after the unplanned reactor trip on December 31, 1992. Unit I reactor was taken critical on January 3 at j
0152 EST and was online at 1039 EST on January 4.
Unit 1 reached 100 percent j
reactor power at 0135 EST on January 6 and. operated at approximately 100
]
percent reactor power through the end of' January.
4 i
UNIT 2 4
j Unit 2 generated 506,475 MWh (gross) electrical power during January with a capacity factor of 58.58 percent.
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Unit 2 remained in Mode 3 at the beginning of January after the unplanned 1-reactor trip on December 31, 1992. ' Unit 2 was taken critical on January 2 at 1447 EST and was at 13 percent reactor power.on January'3 at.0713 EST.
On' January 4 at 0853 EST, the decision was made ti remove the "B" phase generator 4
i bushing and replace it before returning Unit 2 to -service. Unit 2 reactor
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power level was reduced to 8 percent.
j On January 7 at 0050 EST, a Unit 2 shutdown was initiated to allow further-investigation of the control circuit on the centrifugal charging pump suction valves. Unit 2 entered Mode 3 at 0105 EST.
i.
Unit 2 was taken critical on January 9 lat 1808 EST, and was returned to j
service on January 10 at 0256 EST. Unit 2 reached 100' percent power on January 13 at 2230 EST.-
1
!j On January 28 at 1200 EST, a Unit 2 reactor power decrease _was initiated to repair a leak on an extraction steam line._ On January 29 at 0416 EST, with reactor power at approximately 30-percent', the decision was made to take 3
11 Unit 2 to Mode 3 to allow permanent-pipe repair of the steam. leak and ehe t
repair of a main generator hydrogen leak, b
Unit 2 was removed-f rom service at 0645 m EST on January 29 and. entered Mode 3.
After maintenance was completed, Unit 2 was taken critical at 1753 EST on 4
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- January 30 and was online at 1204 EST on January.31'. Unit 2.was at 43 percent-j.
reactor power at the end.of January.
h POWER-OPERATED RELIEF VALVISJEQRVs) AND SAEEILVAINES EUMMAla There were no challenges to PORVs or-safety valves in January.
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AVERAGE IMILY UNIT POWER LEVEL DOCKET NO.
_.50-327 UNIT No. _One DATE:.31 02:93 COMPLETED BY L_J._llo.110 mon TELEPllONE: 1615)_&h3-Z528 MONTil JANUARL1993._.
-l AVERAGE DAILY POWER LEVEL AVERAGE DAILY l'0WER LEVEL DAY
_{MWe.liet )
DAY (tNe:Neil 1
-29 17 1153 2
-32 18 1150 J
3
-19 19 115.2 4
87 20 1153 5
651 21 Il12 6
112Z 22 1154 7
1139 23 1154 1
8
_1139 24 115.4_
9 1139 25 1151 j
10 1146 26 1152 11 1151 27 1152 12 1152 28 1149 13 1152.
29 1144 14 1151 30 1145 15 1152 31 1149 16 1152
AVERAGE IMILY UNIT POWER LEVEL 4
DOCKET NO.
_50-328 UNIT No.,_Ivo DATE:
_01.02.-3 1 COMPLETED BY:
L_L_Jiollomon TELEP110NE 1611)_8t 3-Z128 t
MONTil JAtWARL199JL_
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DA1 ONe-Net)
DAY (tMe-Net) 1
-29 17 1135 2
-32 18 1135 3
-29 19 1135 4
-27 20 1135 5
-l6 21 1135 6
-18 22 1135 7
-11_
23
_1135 8
-19 24 1134 9
-15 25 1131 10 294 26 1132 11 1066 27 1131 12 1089 28 945 13 103 1 29 71 14 1132 30
-16 15 1141 31 101 t
16 1133
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- l.,
f OP[ RATING DATA REPORT s
DOCKET NO.
50-327 DATE 02/08/.93 COMPLETED BY L_J4_tiollomon._
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TELEPHONE 1615) 843.l}Z L 1
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QELEAllHG STATU$
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l Notes l
1.
Unit Name: _$eguaya.ttt) nit One l
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2.
Repor;ing Period: JAnyary 1993 l
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3.
Licensed Thernial Power (HWt): _3411.0 l
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Nameplate Rating (Gross HWe): _122016 l
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Design Electrical Rating-(Net HWe): _1.]48.0 l
l 6.
Maximum Dependable Capacity (Gross HWe): _11hla -
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7.
Maximum Dependable Capacity (Net HWe): W22. 0 _.
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g 8.
If Changes Occur in capacity Ratings (Item Numbers 3 through 7) Since Last Report, Give Reasons::
t 9.
Power tevel To Which Restricted, If Any (Net HWe):
N/A l
l
- 10. Reasons For Restrictions, if Any:
N/A i
l This Month Yr-to-Date Cumulative j
l'
- 11. Hours in Reporting Period
_ _ 144 744 101J93 l
- 12. NurbeF cf Hourt Reactor Was Critical
_ 6.93 1. _
694.1_
55.442 i
- 13. Reactor Reserve Shutdown Hours 0
0 0'
i4. Hours Generator _On-Line Mid 661.4
_ % 219, L i
- 15. Unit Reserve Shutdown Hours
_Q,0 0
0 3
- 16. Gross Tlarmal Energy Generated (HWH).
Lind99f -
2.195.L99.6_
177.173.4JA i
- 17. Gross tiectrical Energy Generated (HWH) __JLL930, 762.990...
60.107.104 3
- 18. Net flectrical Energy Generated (HWH)
_133,3A8 733.348 57.655.570
- 19. Unit S.vice Factor 88 9 88.9 5"l,1_
- 20. Unit Availability factor.
88.9 88.9 53.4-
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- 21. Unit Capacity factor (Using HDC Net) 87.9 87.9 50.6
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- 22. Unit Capacity Factor (Using DER Net) 85.9 85.L 49.4 j
- 23. Unit forced Outage Rate 1111 11.1 38.3 1'
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
j The Cyi]LLtefueling_Quiage_11_ichedaleLio_begiftonJaril' 16. 1993._wilita_ dural.icn._of 65'-
dn12x L
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup l
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OPERATING DATA REPORT DOCKET NO. _$Q-J28 DATE _02L00/93 COMPLETED DY L_L BallDm01L.
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TELEPHONE lillL143-ZEES._
OtLRAL11tGlIALV5 l Notes l
1.
Unit Name: _1ggu9Jah Unit Jyo l
l 2.
Reporting Period: _ January _.1293.
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3.
Licensed Thermal Power (HWt): _341LO l
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Nameplate Rating (Gross HWe): _l?Z0d l
l Design Electrical Rating (Net HWe): 11.400 l-l 6.
Maximum Dependable Capacity (Gross HWe): _.1162 0 l
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7.
Maximum Dependable Capacity (Net HWe): 111L0 l
l
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8.
If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) $1nce Last Report. Give Reasons:
1 j
9.
Power Level To Which Restricted. If Any (Net HWe):
N/A
- 10. Reasons for Restrictions, If Any:
N/A l
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This Month Yr-to-Date Cumulative s
- 11. Hours in Reporting Period 744 744 93.553
- 12. Number of Hours Reactor Was Critical 605.5..
605.5_.
56 819
- 13. Reactor Reserve $hutdown Hours 0
0 0 _.
4
- 14. Hours Generator On-Line 471.8 471.8 55.54L2_
4
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross Thermal Energy Generated (HWH) 1.516.519.5 1.516 dlL $_
174.690.299 4
- 17. Gross Electrical Energy Generated (HWH)
_ 106.475 506m475.
__12.229.594
- 18. Net Electrical Energy Generated (HWH)l-4BL998 48L298._ _.
,$Lh28.273
- 19. Unit Service factor 63.4 63._4_
59x4_
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- 20. Unit Availability Factor 63.4 63.4 59.4
- 21. Unit Capacity Factor (Using HDC Net) 57.9 57.9
- 54. Q_,_
- 22. Unit Capacity Factor (Using DER Net) 56.5 56.5 52,6_.
I
- 23. Unit forced Outage Rate-36.6 3Q.
33.2-
- 24. Shutdowns Scheduled Over Next 6 Honths (Type. Date, and Duration of Each):
j
' 25, If Shut-Down At End Of Report Period. Estimated Date of Startup:
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o DCCKET NO:
50-327 U3IT SHUTDOWNS AND POWER REDUCTIONS UNIT PGNE:
One DATE:
02/08/93 REFORT HONTH: JANUARY 1993 COPPLETED BY:T. A Ho11omon TELEPHONE:i615) 8e:3-7523 i "
Method of Licensee Cause and Corrective i
Duration Shutting Down Event System Component Action to l
2 3
5 f
j' No.
Date Type (Hours)
Reason Reactor Report No.
Code #
Code Prevent Recurrence t
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Unit I was in Mode 3 at the beginning of January. Unit 1 1-was returned to service on January 4.
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e I: Forced Reason:-
hthod:
2 F
Exhibit G-Instructions 4
'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 (MJREG-1022)
E-Operator Training and License Examination 5-Reduction
-T-Adrinistrative 9-Other 5
G-Operational Error (Explain)
Exhibit I-Same Source H-Other -(Explain) i j.
_ _ _ _ _.. ~.
DCEKET NO:
50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
Two DATE:
02/08/93 REPORT MONTH: JAPUAaY 1093 EOMPLETED BY:T 3 McIlossta TELEPHONE:f6151 843-7528.
Method of Licensee Cause and Corrective Action to Duration Shutting Down Event Systgm C q nent No.'
Date Type (Hours)
Reason Reactor Report No.
Code Code Prevent Recurrence Unit 2 was in Mode 3 at the beginning of January. On January (, Unit 2 was taken critical and reached 13 percent power on January 3.
On January 7 at 0050 EST, a Unit 2 shutdown was initiated to allow investigation of the control circuitry on the centrifugal charging pump suction valves. The control circuitry was determined to be correct. Unit 2 entered Mode 3 at 0105 EST.
12 930128 F
53.3 B
1 N/A SB PSF On January 23 at 1200, a power TK PSF decrease was initiated to repair a leak on an extraction steam 1ine. Unit 2 was removed from service at 0645 EST on January 29 and entered Mode 3 for maintenance on the AZ MSR steam leak and repair of.a main generator hydrogen leak.
The extraction steam line leak was the result cf erosion and the affected segments of piping were replaced. The generator hydrogen leak was caused by a failure of a gasket at a flange connection. The gasket was replaced and the system was returned to service. Unit 2 was returned to service on January 31.
I 2
3 I: Forced Reason:
Method:
Exhibit G-Instructions F
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 (NURES-1022; E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other SEnhibit I-Same Source
.Wrational Error (Explain)
H-Other (Explain)
._