ML20202J791
| ML20202J791 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 01/31/1998 |
| From: | Hollomon T, Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9802230220 | |
| Download: ML20202J791 (10) | |
Text
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e e.
k Tennessee Valley Authority, Post Omce Box 2000, Soddy-Daisy, Temossee 37379-20C0 February 17, 1998 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matte. of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - w 'TUARY 1998 MONTHLY OPERATING REPORT Enclosed is the January 1998 Monthly Operating Report as required by SON Technical Spec lication 6.9.1.10.
If you have any questions concerning this matter, please telephone me at (423) 843-7170 or J.
D.
Smith at (423) 843*6672.
Sinuarely, t.
dalas Licensing and Industry Affairs Manager Enclosure cc:
See page 2 II hI gRO2230220 980131 q
ADOCK 05000327 PDR h
,I
i e
U.S. Nuclear Regu'.atory Commission Page 2 February 17, 1998 cc (Enclosure):
Mr. R.- W. Hernan, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5947 Ms. Barbara Lewis, Assistant Editor, Database McGraw-Hill, Inc.
1200 G Street, NW, Suite 1100 Washington, D.C.
20005 Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igor Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S.
Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30303-3415 b
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TENNESSEE VALLEY 4UTHORITY SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION JANUARY 1998 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 2
r-
E OPERATIONAL
SUMMARY
JANUARY 1998 UNIT 1 Unit 1 generated 885,528 megawatthours (MWh) (gross) electrical power during January with a capacity factor of 103.05 percent.
There were no outages or power reductions of greater than 20 percent in the average daily power level during January.
Unit I was operating at 100 percent power at the end of January.
UNIT 2 Unit 2 generated 880,978 MWh (gross) electrical power during January with a capacity factor of 102.52 percent.
There were no outages or power reductions of greater than 20 percent in the average daily power level during January.
Unit 2 was operating at 100 percent power at the end of January.
SUMMARY
OF POWER-OPERATED RELIEF VALVES (PORVs)
AND SAFETY VALVES CHALLENGES No PORVs or safety valves were challenged in January.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-327 UNIT NO.
One DATE:
02-09-98 COMPLETED BY:
T. J. IIollomon TELEPIIONE: (423) 843-7528 MONTil: JANUARY 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL.
DAY (MWe-Net)
DAY (MWe-Net) 1 1153 17 1153 2
1153 18 1154 3
-1153 19 1153 4
1156 20 1156 5
1153 21 1154 6
1152 22 1156 7-1153 23 1153 8
1153-24 1153 9
1153 25 1153 10 1154 26 1153 11 1154 27 1153 12 1154 28 1151 13 1153 29 1153 14 1153 30 1155 15 1156 31 1154 16 1153
,a AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50 328 U111T NO.
Two DATE:
02-09-98 COMPLETED BY:
T. J. IIollomon TELEPHONE: (42M 843-7528 MONTil: JANUARY 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 1151 17 1152 2
1151 18 1152 3
1151 19 1150 4
1151 20 1149 5-1152 21 1152 6
1149 22 1152 7
1149 23 1153 8
1149 24 1151 9
1152 25 1153 10 1152 26 1153 11 1153 27 1141 12 1151 28 1151 13 1148 29 1151 14 1151 30 1153 15 1150 31 1153 16 1150
OPERATING DATA REPORT DOCKET NO. 50-327 DATE 02/09/98 COMPLETED BY T. J. IIollomon TELEPliONE (423) 843-7528 OPERATING STATUS
- 1. Unit Name:
Sequoyah Unit One
- 2. Reporting Period:
January 1998 l
- 3. Licensed Thermal Power (MWt):
3411.0
- 4. Name-late Rating (Gross (MWe):
1220.6
- 5. Design Electrical Rating (Net MWe):
1148.0
- 6. Maximum Dependable Capacity (Gross MWe):
1155.0
- 7. Maximum Dependable Capacity (Net MWe):
1117.0
- 8. If Changes occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, if Any (Net MWe):
N/A
- 10. Reasons for Restrictions,If Any: N/A This Month Yr.-to-Date Cumulative i1. Ilours in Reporting Period 744 744 145,417
- 12. Number of11ours Reactor Was Critical 744.0 744.0 85,600
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Ilours Generator On Line 744.0 744.0 S3,803.6
- 15. Unit Reserve Shutdown 11ours 0
0 0
- 16. Gross Thermal Energy Generated (MWh) 2,536,111.9 2,536,111.9 273,780,108
- 17. Gross Electrical Energy Generated (MWh) 885,528 885,528 93.286.655
- 18. Net Electrical Energy Generated (MWh)-
857,976 857,976 89,557,873
- 19. Unit Service Factor 100.0 100.0 57.6
- 20. Unit Availability Factor 100.0 100.0 57.6
- 21. Unit Capacity Factor (Using MDC Net) 103.2 103.2 55.1
- 22. Unit Capacity Factor (Using DER Nu) 100.5 100.5 53.6
- 23. Unit Forced Outage Rate 0.0 00 29.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
__u
OPERATING DATA REPORT DOCKETNO. 50 328 DATE 02/09/98 COhiPl.liTED llY T. J. llollomon TEl.EPlIONE (423) 843-7528 Ofl3(A'lINQSTA I US
- 1. Unit Nmre:
Scouovah Unit Two
- 2. Reportir.g Period:
January 1998 1.1.icensed Thermal Power (hiWt):
3411.0
- 4. Nameplate Rating (Gross (h1We):
1220.6
- 5. Design Electrical Rating (Net h1We):
I148.0
- 6. hiaximum Dependable Capacity (Gross htWe):
1155.0 7 hiaximum Dependable Capacity (Pet h1We):
1117.0
- 8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 9. Pov...I Level to Which Restricted. if Any (Net hiWe):
N/A
- 10. Reason'; for Restrictions, if Any: N/A This hionth Yr. to Date Cumulative 11, llours in Reporting Period 744 744 137,377
~
12, Number ofIfours Reactor Was Critical
?44.0 744.0 88,399 11 Reactor Reserve Shutdown llours 0
0 0
- 14. llours Generator On Line 744.0 744,0 86,418.5
- 15. Unit Reserve Shmdown llours
')
0 0
- 16. Gross Thermal Energy Genermed (h1Wh) 2,536,128.0 2,536,128.0 276,513,464
- 17. Gross Electrical Energy Generated (h1Wh) 880,978 880,978 94,106,342
- 18. Net Electrical Energy Generated (htWh) 855,946 855,946 90,261,308
- 19. Unit Service Factor 100.0 100.0 62.9
- 20. Unit Availability Factor 100.0 100.0 02.9 21 Unit Capacity Factor (Using h1DC Net)
L.0 103.0 58.3
- 22. Unit Capacity Factor (Using DER Net) 100.2 100.2
$ 1.2
- 23. Unit Forced Outage Rate 0.0 0.0 29.0
- 24. Shutdowns Scheduled Over Next 6 hionths (Type, Date, and Duration ofliach):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
l
f i
DOCKE1 NO_:
50-327 UNIT NAME:
One i
[
UNIF StiUTDOWNS AND POWER REDUCTIONS DATE-020998 COMPLETED BY:
T. J. IIolkmmn REPORT MONTil: JANUARY 1908 TELEP110NE:
(4231843-7523 j-
~No.
Date Type' Outage Reason Method of Licensee System Component Caase and Correcuve Acton to Ibtnt 2
Duration Stu%g Event Report Code' Code' Recurrence I
(flours)
Down No.
j j
Reactor' l
There were no octages or r arr reductions of greater than 20 percent in the astrage l
daily peuer levei during the month.
1 i
2 l
4 i
f l
I E
i
'F: Forced Reasan:
' Method
- E ".ibit G-Instructens i
2 S: Scheduled A-Equipment Failure (Explain)
I-Manual for Preparation of Data
[
B-Maintenance or Test 2-Manual Scram Entry sheets fiw Licensee C-Refueling 3-Automatic Scram Event Report (LER) File l
D-Regulatory Restriction 4-Continuaton of Existing Outage (NUREG-1022) i E-Operator Training and License Exam 5-Reduction i
F-Administrative 9-Other
' Exhibit I-Same Source G-Operational Error (Explain) li-Other (Explain)
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l DOCKET NOc 50-328 UNIT NAME-Two
{
UN1iSliUTDOWNS AN7 POWER REDUCTIONS DATE:
02 Tr098 l
COMPLETED BY:
T. J. Iloikwnon REPORT MONT11: JANUARY 1993 TELEPliONE:
(4231 843-7528 i
t r'
No.
Date Type' Outage Reason; Method of Licensee System Component Cause and Corrective Action to Prevent Duration Shutting Event Code' Code' Recurrence I
(1 fours)
Down Rep t No.
Reactor' There were no outages or power reducions of greater than 20 percent in the average
[
daily power level dusig the month.
L l
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2 I
i 4
Reason:
' Method
- Exhibit G-Instructions
'F: Forced 2
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 7-Manual Scram Entry sheca for Licensee
[
i C-Refbeting 3-Automat.c Scram Event Report (LER) File I
D-Regulatory Restnction 4-Continuation of Existing Outage (NUREG-1022)
[
E-Operator Training and License Exam 5-Reducten F-Administrative 9-Other
' Exhibit I-Same Scarce G-Operational Error (Explain)
II-Other(Explain) f r
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