ML20141H307
| ML20141H307 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1997 |
| From: | Hollomon T, Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9707220328 | |
| Download: ML20141H307 (10) | |
Text
IUA Tennessee Valley Authority, Post Omca Box 2000, Soddy-Daisy Tennessee 37379-2000 July 14, 1997 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos.50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - JUNE 1997 MONTHLY OPERATING REPORT Enclosed ia the June 1997 Monthly Operating Report as required by SON Technical Specification 6.9.1.10.
If you have any questions concerning this matter, please telephone me at (423) 843-7170 or James D. Smith at (423) 843-6672.
7 Si ogg-Pedro Salas Site Licensing and Industry Affairs Manager gl Enclosure cc:
See page 2 970'7220328 970630 PDR ADOCK 05000327 R
PDR k!,!k !k
Y c U.S. Nuclear Regulatory Commission
.Page 2-
}
July.14, 1997 cc -(Enclo'sure) :
I Mr. :R. W..Hernan,. Project Manager U.S. Nuclear Regulatory Commission One White. Flint, North
.11555'Rockville Pike Rockville, Maryland 20852-2739 1
i INPO Records Center Institute of Nuclear Power Operations.
~700 Galleria Parkway.
Atlanta, Georgia 30339-5947 1
Ms.-Barbara Lewis,1 Assistant Editor, Database-
[
McGraw-Hill,'Inc.
1200 G Street, NW, Suite 1100 Washington, D.C.
20005 Mr. James Lang, Manager Advanced Reactor Department' l_
Electric Power Research Institute
).
3340 Hillview Avenue Palo Alto, California 94304 1
i NRC Resident Inspector-Sequoyah Nuclear Plant f=
2600 Igou Ferry Road
. Soddy-Daisy, Tennessee 37379-3624-
+
[
Regional Administrator l
U.S. Nuclear Regulatory Commission
)
Region II
' Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 E
Atlanta, Georgia 30323-3415
4 3
4 i
TENNESSEE VALLEY AUTIIORITY f
SEQUOYAII NUCLEAR PLANT 4
MONTHLY OPERATING REPORT 4
TO TIIE
.f l
NUCLEAR REGULATORY COMMISSION JUNE 1997 i
i UNIT 1 DOCKET NUMBER 50-327 4
LICENSE NUMBER DPR-77 UNIT 2 1
DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 i
1
j s
OPERATIONAL
SUMMARY
JUNE 1997 l
i i -
UNIT 1 Uni +. 1 generated 829,950 megawatthours (bmh) (gross) electrical power l
du'ing June with a capacity factor of 99.8 percent.
On June 28 at 1852 r.JT, a. power reduction to 62 percent was initiated for planned maintenance on the 1B-B main feed pump to repair an oil leak.
Reactor power increase was initiated on June 30 at 0745 EDT, and Unit 1 was operating at 100 percent reactor power at 2230 EDT that day and through the end of June.
p i
UNIT 2 Unit 2 generated 793,742 megawatthours (MWh) (gross) electrical power during June with a capacity factor of 95.4 percent.
On June 5 at 1347
]
EDT, an alarm was received on letdown heat exchanger flow temperature abnormal.
Investigation showed that a letdown flow control valve had closed.
Excess letdown was established.
The flow control valve closed as a result of a degraded actuator diaphragm.
On June 6 at 1633 EDT, a i
power decrease was initiated and reactor power was stabilized at 2 -
approximately 28 percent on June 7 at 1557 EDT.
Reactor power increase was initiated on June 8 at 1638 EDT, and Unit 2 was operating at 100 percent power on June 9 at 2330 EDT.
On June 18 at 2007 EDT, a reactor power decrease was initiated to remove 2B main feed pump from service to repair a leaking seal water injection header that could not be isolated.
Power was stabilized at 56 percent on June 19 at 0155 EDT and repairs were completed.
Reactor power increase was initiated on June 19 at 0515 EDT, and Unit 2 was operating at 100 percent power on June 19 at 1727 EDT.
Unit 2 continued to operate at 100 percent reactor power through the end of June.
SUMMARY
OF POWER-OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES CHALLENGES No PORVs or safety valves were challenged in June.
4 I
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g
4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT NO.
One DATE:
07-07-97 COMPLETED BY: T. J. Hollomon TELEPHONE: (423) 843-7528 MONTH: JUNE 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net)
J l
1144 17 1142 2
1143 18 1142 3
1136 19 1142 4
1133 20 1140 5
1133 21 1144 6
1143 22 1141 7
1146 23 1139 8
1149 24 1138 9
1144 25 1138 10 1143 26 1137 11 1145 27 1139 12 1147 28 1079 13 1144 29 674 1
-14 1144 30 876 15 1144 31 NA 16 1142
. s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT NO.
Two DATE:
07-07-97 COMPLETED BY: T. J. Hollomon TELEPHONE: (423) 843-7528 MONTH: JUNE 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 1142 17 1136 2
1133 18 1116 3
1143 19 943 4
1140 20 1136 1
5 1137 21 1136 6
1072 22 1135 7
379 23 1130 8
261 24 1134 9
1003 25 1133 10 1137 26 1127 11 1140 27 1127 12 1140 28 1126 13 1139 29 1127 14 1136 30 1128 15 1138 31 NA 16 1138
OPERATING DATA REPORT i
DOCKET NO. 50-327 DATE 07/07/97 COMPLETED BY T. J. Hollomon TELEPHONE (423) 843-7528 OPERATING STATUS
- 1. Unit Name:
Seauovah Unit One
- 2. Reporting Period:
June 1997
- 3. Licensed Thermal Power (MWt):
3411.0
- 4. Nameplate Rating (Gross (MWe):
1220.6
- 5. Design Electrical Rating (Net MWe):
114R0
- 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
- 11. Hours in Reporting Period 720 4,343 140,256
- 12. Number ofHours Reactor Was Critical 720.0 3,141.3 80,464
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 720.0 3,104.3 78,675.9
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWh) 2,399,755.2 9,977,676.1 256,332,663
- 17. Gross Electrical Energy Generated (MWh) 829,950 3,473,223 87,265,363
- 18. Net Electrical Energy Generated (MWh) 803,462 3,348,875 83,726,513
- 19. Unit Service Factor 100.0 71.5 56.1
- 20. Unit Availability Factor innn 71.5 56.1
- 21. Unit Capacity Factor (Using MDC Net) 99.9 69.0 53.4
- 22. Unit Capacity Factor (Using DER Net) 97.2 67.2 52.0
- 23. Unit Forced Outage Rate 0.0 0.0 31.2
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End ofReport Period, Estimated Date of Startup:
N/A 1
l l
. /.
.o*
OPERATING DATA REPORT DOCKET NO. 50-328 DATE ' 07/07/97 COMPLETED BY T. J. Hollomon TELEPHONE (423) 843-7528 OPERATING STATUS
- 1. _ Unit Na'.ne:
Seouovah Unit Two 4
I June 1997
- 2. Reporting Period:
~
3411 0
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross (MWe):
1220 6
- 5. Design Electrical Rating (Net MWe):
1148 0 i
- 6. Maximum Dependable Capacity (Gross MWe):
1155.0
- 7. Mr.ximum Dependable Capacity (Net MWe):
1117.0
- 8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
l
- 9. Power Level to Which Restricted, If Any (Net MWe):
N/A
- 10. Reasons for Restrictions, If Any: N/A l
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 4,343 132,216 L
- 12. Number of Hours Reactor Was Critical 720.0 4,343.0 83,945
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator Oa-Line 720.0 4,343.0 82,015.5
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWh) 2,315,918.4 14,620,226.3 262,359,880
- 17. Gross Electrical Energy Generated (MWh) 793,742-5,050,609 89,249,666 L
- 18. Net Electrical Energy Generated (MWh) 767,646 4,885,157 85,564,876
- 19. Unit Service Factor 100.0 100.0 62.0 20; Unit Availability Factor 1000 100.0 62.0
- 21. Unit Capacity Factor (Using MDC Net) 95.4 100.7 57.9
- 22. _ Unit Capacity Factor (Using DER Net) 92.9 98.0 56.4 23, Unit Forced Outage Rate 0.0 0.0 30.1 lt
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Unit 2 Cycle 8 Refueling 1
Outage is scheduled to begin in October 3.1997 with a duration of 50 days.
l
- 25. If Shut Down At End ofRepon Period, Estimated Date of Stanup:
N/A l
l s
/i
DOCKET NO.: 50-327 6
UNITNAME ' One UNIT SHUTDOWNS AND POWER REDUCTIONS
. DATE: 07/07/07 COMPLETED BY:
T. J. Hollomon REPORT MONTit _JU_NE 1997 TELEPHONE: (423) 843-7528.
No.
Date Type' Outage Reason Method of Licensee System Component Cause and Corrective Action to Prevent Duration Shutting Event Report Code Code' R-nac.
d (Hours)
Down No.
Reactor' 3
970628 S
N/A B
5 N/A N/A N/A On June 28 at 1852 EDT, a power reduction to 62 percent was initiated for planned maintenance on the IB-B main feed pump to repair an oilleak.
4
'F: Forced Reason:
' Method
' Exhibit G-Instructions 2
S: 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 Restriction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Exam 5-Reduction 5
F-Administrative 9-Other Exhibit I-Same Source G-Operational Error (Explain)
H-Other(Explain) r l
c v<
=
---_-__,_m_____..___-_a________
m
~ _... _ - - - - - _ - _ - _
DOCKET NO.: 50-328 UNIT NAME: Two
}*[
l UNTT SHIIIDOWNS AND POWER PEDUCTIONS DATE: 07/07/97 COMPLETED BY:
T. J. Hollomon
' REPORT MONTH: JUNE 1997 TELEPHONE: (423) 843-7528 2
No.
Date Type' Outage Reason Method of Licensee System Component Cause and Corrective Action to Present Duration Shutting Event Code Code' Recurrence d
(Hours)
Down Report No.
Reactor' f
1 970605 F
N/A A
5 N/A N/A N/A On June 5 at 1347 EDT, an alarm was received on letdown heat exchanger flow.
temperature abnormal Investigation showed that the letdown flow control valve 2-FCV-62-69 had closed. Excess letdow11 was i
established. It was determined that the diaphragm had failed on the valve. The t
valve was repaired and the system was returned to senice.
2 970618
.F N/A A
5 N/A N/A N/A' On June 18 at 2007 EDT, a reactor power decrease was initiated to remost 2B main feed pump from senice. The seal water injection header was leaking and could not be isolated. Repair of the line was l
performed and the system was returned to senice.
A
'F: Forced Reason:
' Method
' Exhibit O-Instructions 2
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation ofData -
B-Maintenance or Test 2-Manual Scram
- Entry sheets for Licen.see C-Refueling
' 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Exam 5-Reduction a
5 F-Administrative 9-Other Exhibit I-Same Source G-Operational Error (Explain)
- H-Other (Explain)
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