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- *' (e , '* .,e il' t | |||
p . | |||
En tennessee Vaney Authuitt. Post Off<te Box 20C0 Scday Daisy Tennessee 37379 i | |||
't March 15, 1995 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) - FEBRUARY 1995 MONTHLY OPERATING REPORT .l l | |||
Enclosed is the February 1995 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10. | |||
If you have any questions concerning this matter, please call l J. W. Proffitt at (615) 843-6651. I i | |||
Sincerely, i | |||
N R. H. Shell ( | |||
Manager SQN Site Licensing ; | |||
Enclosure cc See page 2 21020e 98 9503210509 950228 ' | |||
l ! | |||
gDR ADOCK 05000327 PDR | |||
$. ;. j, ; - - | |||
.. = | |||
U.S. Nuclear Regulatory Commission 2 .Page 2 March.15, 1995 cc (Enclosure): | |||
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear. Regulatory Commission One White. Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Joseph Santucci, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue ! | |||
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, NW, Suite 2900 Atlanta, Georgia 30323-2711 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, suite 2900 , | |||
Atlanta, Georgia 30323-2711 Mr. F. Yost, Director Research Services Utility Data Institute 1200 0 Street, NW, Suite 250. | |||
Washington, D.C. 20005 | |||
< , 1 | |||
/ | |||
, '!' ji 4: | |||
'I g, t TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT i | |||
MONTHLY OPERATING REPORT . | |||
TO THE NUCLEAR REGULATORY COMMISSION FEBRUARY 1995 l | |||
J UNIT 1 I | |||
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 ; | |||
4 l | |||
UNIT 2 DOCKET NUMBER 50-328 l | |||
LICENSE NUMBER DPR-79 l | |||
* ;.) r x , . | |||
f . | |||
4 OPERATIONAL | |||
==SUMMARY== | |||
FEBRUARY 1995 , | |||
1 | |||
) | |||
UNIT 1 1 | |||
. Unit 1 generated 639,850 megawatthours (MWh) (gross)' electrical power during February with a capacity factor of 82.7 percent. , | |||
On February 23 at approximately 1600 EST, with the reactor operating at | |||
~ | |||
j 100 percent power, Unit 1 experienced a reactor coolant system (RCS) leak . | |||
at a compression fitting on a reactor vessel level indicating system 1 (RVLIS) line in the incore instrument room. A notice of unusual event ; | |||
was declared at 1715 EST as a result of an RCS unidentified leakage.in { | |||
excess of the technical specification limit. At 1717 EST, an emergency ; | |||
shutdown was initiated. The generator was taken offline at 1811 EST, and l Unit 1 entered Mode 2 at 1810 EST. The Unit-1 reactor was taken subcritical, and the reactor trip breakers were opened at 1826 EST. On , | |||
FebruaLy 24 at 0029 EST, Unit 1 entered Mode 4. | |||
Unit 1 remained in Mode 4 through the end of February as inspection continued on RVLIS compression fittings. I UNIT 2- J Unit 2 generated 784,510 megawatthours (MWh) (gross) electrical power $ | |||
during February with a capacity factor 99.3 percent. Unit 2 operated at near 100 percent reactor power throughout the month of February. | |||
i l | |||
1 I | |||
''a' 'E s | |||
r AVERAGE DAILY UNIT POWER. LEVEL ' | |||
DOCKET NO. 50-327 UNIT No. -One .DATE: _Q)-02-95' | |||
'I' COMPLETED BY: T. J. He11omo.D TELEPHONE: f6151 843-7528 MONTH: FEBRUARY 1995 | |||
,s AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL' f Rh1 (MWe-Net) Rh1 (MWe-Net) 1 1149 17 1127 2 i ' ', L_ 18 998 1153 1041 I 3 19 4 1143 20 1147 , | |||
5 1146 21 1151 | |||
* 6 1153 22 1154 l 7 1150 23 851 8 1149 24 -28 9 1149 25 -30 10 1150 26 -28 ; | |||
11 1151 27 -26 ; | |||
12 , | |||
1150 28 -28 13 1151 29 N/A 14 1154 30 N/A 1 15 1151 31 N/A 16 1150 l | |||
.. _ . . .m .. . _. - . . , | |||
1d[ | |||
s -l , , | |||
# - 4 if 4' AVERAGE DAILY UNIT POWER LEVEL , | |||
1 | |||
~ DOCKET NO. 50-328 UNIT No. 'Two DATE: 03-02-95 v. | |||
- COMPLETED BY: T. J. Hollomon TELEPHONE: f615) 843-7528 ! | |||
t MONTH: FEBRUARY 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVELD l R&l -' fMWe-Net) QAl- (MWe-Net) 1 1140 17 1137 2 1139 18 1132 3 1140 19 1138 4 1137 20 1137 _ | |||
i S 1139 21 1137 6 1136 22 1140 , | |||
7 1136 23 1138 | |||
. 8 1136 24 1142 , | |||
9 1139 25 1143 I | |||
10 1110 26 1142 5 1 | |||
11 1108 27 1143 12 1107 28 1143 13 1113 29 N/A l 14 1119 30 N/A I 15 1121 31 N/A 16 1112 l | |||
+ | |||
4 1 | |||
l l | |||
l | |||
,o . , . | |||
+ | |||
. OPERATING DATA REPORT DOCKET NO. 50-327 DATE 03/02/95 COMPLETED BY T. J. Hollomon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l | |||
: 1. Unit Name: Seavovah Unit One l l | |||
: 2. Re, m Ung Period: February 1995 l [ | |||
: 3. Licensel Thermal Power (MWt): 3411.0 l l | |||
: 4. Namepiste Rating (Gross Hde): 1220.6 l l | |||
: 5. Design Electrical Rating (Net MWe): 1148.0 l l | |||
: 6. Maximum Dependable Capacity (Gross MWe): 1151.0 ___ l l | |||
: 7. Maximum Dependable Capacity (Net HWe): 1111.0 l ! | |||
: 8. If Ct.anges Occur in Capacity Ratings (Item Numbers 3 Through 7) $1nce 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 672 1.416 119.785 | |||
: 12. Number of Hours Reactor Was Critical 546.4 1.290.4 63.340 | |||
: 13. Reactor Reserve Shutdown Hours C 0 0 | |||
: 14. Hours Generator On-Line 546.2 1.290.2 61.894.5 | |||
: 15. Unit Reserve Shutdown Hours 0 0 0 ,___ | |||
: 16. Gross Thermal Energy Generated (MWH) 1.837.960.3 4.371.863.7 .20116; 860 | |||
: 17. Gross Electrical Energy Generated (MWH) _ 639.850 1.524.710 68.575.594 | |||
: 18. Net Electrical Energy Generated (MWH) 616.194 1.473.880 65.737.293 | |||
: 19. Unit Service Factor 81.3 91.1 51.7 - | |||
: 20. Unit Availability Factor 81.3 91.1 51.7 | |||
: 21. Unit Capacity Factor (Using MDC Net) 82.5 93.7 49.4 | |||
: 22. Unit Capacity Factor (Using DER Net) 79,9 90.7 47.8 | |||
: 23. Unit Forced Outage Rate 18.7 8.9 36.2 | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): | |||
: 25. If Chut Down At End Of Report Period, Estimated Date of Startup: | |||
l l | |||
\ | |||
*;0 l' * [ . . | |||
f- +. - | |||
OPERATING DATA' REPORT- , | |||
DOCKET NO. 50-328 | |||
[m DATE= 03/02/95 COMPLETED BY T. J. Hollomon TELEPHONE -(615) 843-7528 3 OPERATING STATUS. | |||
l Notes l ' | |||
: 1. Unit Name: Seauovah Unit Two -l l | |||
: 2. Reporting Period: February 1995 l -l | |||
. 3. Licensed Thermal Power (MWt): 3411.0 l l- | |||
: 4. Nameplate Rating (Gross MWe): 1220.6 l l- ; | |||
-S. Design Electrical Rating (Net HWe): 1148.0 l l | |||
: 6. Maximum Dependable Capacity.(Gross MWe): 1146.0 l l i | |||
: 7. Maximum Dependable Capacity (Net MWe): 1106.0 l I | |||
: 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 i | |||
, 10. Reasons For Restrictions, If Any: N/A : | |||
l This Month Yr-to-Date Cumulative. , | |||
: 11. Hours in Reporting Period 672 1.416 111.745 4 | |||
: 12. Number of Hours Reac'or. Was Critical 672.0 1.393.7 65.750 | |||
: 13. Reactor Reserve Shutdown Hours 0 0 0 | |||
: 14. Hours Generator On-Line 672.0 1.354.7 64.064.4 | |||
: 15. Unit Reserve Shutdown Hours 0 0 0' | |||
: 16. Gross Thermal Energy Generated (MWH) 2,275.606.6 4.473.893.2 202.001.356 | |||
: 17. Gross Electrical Energy Generated (MWH) 784.510 1.537.493 68.545.102 [ | |||
: 18. Not Electrical Energy Generated (MWH) 758.230 1.482.037 65.596.219 | |||
: 19. Unit Service Factor 100.0 95.7 57.3 | |||
: 20. Unit Availability Factor 100.0 95.7 57.3 | |||
: 21. Unit Capacity Factor (Using MDC Net) 102.0 94.6 53.1 | |||
: 22. Unit Capacity Factor (Using DER Net) 98.3 91.2 51.1 | |||
: 23. Unit Forced Outage Rate 0.0 ' 4.3 34.7' | |||
: 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: | |||
1 1 | |||
- " ' - n __.- | |||
DOCKET NO: 50-327 UNIT SHUTE 0WNS AND POWER REDGCTIONS UNIT NAME: One | |||
* DAYE: 03/03/95 REPORT MONTH: Febru a ry 1995 COMPLETED BY:1. J. Hollomon ''. | |||
TELEPHONE:(615) 843-7528' Method of Licensee Cause and Corrective - | |||
Duration Shutting Down Event System Compgnent Action to j No. Date Type l | |||
(Hours) Reason 2 Reactor 3 Report No. Code # Code Prevent Recurrence 1 950223 F 125.8 A 1 50-327/95002 AB N/A At approximately 1600 EST, with the reactor operating at 100 percent power. Unit 1 experienced an RCS leak at a compression fitting on a i RVLIS line in the incore instrument room. This event was initiated by i a failed compression fitting on the | |||
: RVLIS. An inspection of the fitting and tubing indicated that the tubing pulled out of the tee. | |||
The ferrule remained inside the nut attached to the compression tee. | |||
The force required to remove the nut was less than expected indi-cating that the compression fitting was not aroperly assembled. The failed fitting was repaired. | |||
Approximately 450 fittings were ' | |||
inspected; approximately 151 indetenminate fittings were identi-fled. Thirty-nine of the 151 indeterminate fittings were dis-assembled and found to be properly install ed. Therefore, a high level of confidence exists in the reli-ability of the compression fitting joints at Sequoyah. A long-term action plan for the inspection of other systems.and the Unit 2 fittings will be determined. | |||
Fittings that were determined to have incorrectly installed ferrules were corrected as appropriate. | |||
2 Reason: 3 #Exhibit G-Instructions I:F Forced Method: | |||
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Mairtenance 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 Trainica and License Examination 5-Reduction F-Administrative 9-Other 5 | |||
G-Operational Error (Explain) Exhibit I-Same Source H-Other (Explain) | |||
DOCKET NO: '50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS - tmIT NAME: Two ;Ng * | |||
- DATE: 03/03/95 : | |||
REPORT M WTH: February 1995 COMPLETED BY:T. J. Hollanon. Y.' 5 TELEPHONE:(615) 843-7528 Method of Licensee Cause and Corrective = | |||
l, Duration Shutting Down Event Systes. Action to 2 4 Compgeent No. Date Type l (Hours) Reason Reactor Report No. Code Code Prevent Recurrence i | |||
There were no outages or power - | |||
reductions of greater than 20 percent to repcrt during February. | |||
? | |||
s I:F Forced 2 Reason: 3 Method: #Exhibit G-Instructions 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 Continuation of Existing Outage (NOREG-1072) | |||
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other 5 Exhibit G-Operational Error (Explain) I-Same Source | |||
~ | |||
H-Other (Explain) > | |||
e | |||
-__._--___ue- a g,_ _- | |||
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Latest revision as of 05:41, 14 May 2020
ML20081F032 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 02/28/1995 |
From: | Hollomon T, Shell R TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9503210509 | |
Download: ML20081F032 (10) | |
Text
wr -
- *' (e , '* .,e il' t
p .
En tennessee Vaney Authuitt. Post Off<te Box 20C0 Scday Daisy Tennessee 37379 i
't March 15, 1995 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) - FEBRUARY 1995 MONTHLY OPERATING REPORT .l l
Enclosed is the February 1995 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.
If you have any questions concerning this matter, please call l J. W. Proffitt at (615) 843-6651. I i
Sincerely, i
N R. H. Shell (
Manager SQN Site Licensing ;
Enclosure cc See page 2 21020e 98 9503210509 950228 '
l !
gDR ADOCK 05000327 PDR
$. ;. j, ; - -
.. =
U.S. Nuclear Regulatory Commission 2 .Page 2 March.15, 1995 cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear. Regulatory Commission One White. Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Joseph Santucci, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue !
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, NW, Suite 2900 Atlanta, Georgia 30323-2711 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, suite 2900 ,
Atlanta, Georgia 30323-2711 Mr. F. Yost, Director Research Services Utility Data Institute 1200 0 Street, NW, Suite 250.
Washington, D.C. 20005
< , 1
/
, '!' ji 4:
'I g, t TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT i
MONTHLY OPERATING REPORT .
TO THE NUCLEAR REGULATORY COMMISSION FEBRUARY 1995 l
J UNIT 1 I
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 ;
4 l
UNIT 2 DOCKET NUMBER 50-328 l
LICENSE NUMBER DPR-79 l
- ;.) r x , .
f .
4 OPERATIONAL
SUMMARY
FEBRUARY 1995 ,
1
)
UNIT 1 1
. Unit 1 generated 639,850 megawatthours (MWh) (gross)' electrical power during February with a capacity factor of 82.7 percent. ,
On February 23 at approximately 1600 EST, with the reactor operating at
~
j 100 percent power, Unit 1 experienced a reactor coolant system (RCS) leak .
at a compression fitting on a reactor vessel level indicating system 1 (RVLIS) line in the incore instrument room. A notice of unusual event ;
was declared at 1715 EST as a result of an RCS unidentified leakage.in {
excess of the technical specification limit. At 1717 EST, an emergency ;
shutdown was initiated. The generator was taken offline at 1811 EST, and l Unit 1 entered Mode 2 at 1810 EST. The Unit-1 reactor was taken subcritical, and the reactor trip breakers were opened at 1826 EST. On ,
FebruaLy 24 at 0029 EST, Unit 1 entered Mode 4.
Unit 1 remained in Mode 4 through the end of February as inspection continued on RVLIS compression fittings. I UNIT 2- J Unit 2 generated 784,510 megawatthours (MWh) (gross) electrical power $
during February with a capacity factor 99.3 percent. Unit 2 operated at near 100 percent reactor power throughout the month of February.
i l
1 I
a' 'E s
r AVERAGE DAILY UNIT POWER. LEVEL '
DOCKET NO. 50-327 UNIT No. -One .DATE: _Q)-02-95'
'I' COMPLETED BY: T. J. He11omo.D TELEPHONE: f6151 843-7528 MONTH: FEBRUARY 1995
,s AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL' f Rh1 (MWe-Net) Rh1 (MWe-Net) 1 1149 17 1127 2 i ' ', L_ 18 998 1153 1041 I 3 19 4 1143 20 1147 ,
5 1146 21 1151
- 6 1153 22 1154 l 7 1150 23 851 8 1149 24 -28 9 1149 25 -30 10 1150 26 -28 ;
11 1151 27 -26 ;
12 ,
1150 28 -28 13 1151 29 N/A 14 1154 30 N/A 1 15 1151 31 N/A 16 1150 l
.. _ . . .m .. . _. - . . ,
1d[
s -l , ,
- - 4 if 4' AVERAGE DAILY UNIT POWER LEVEL ,
1
~ DOCKET NO. 50-328 UNIT No. 'Two DATE: 03-02-95 v.
- COMPLETED BY: T. J. Hollomon TELEPHONE: f615) 843-7528 !
t MONTH: FEBRUARY 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVELD l R&l -' fMWe-Net) QAl- (MWe-Net) 1 1140 17 1137 2 1139 18 1132 3 1140 19 1138 4 1137 20 1137 _
i S 1139 21 1137 6 1136 22 1140 ,
7 1136 23 1138
. 8 1136 24 1142 ,
9 1139 25 1143 I
10 1110 26 1142 5 1
11 1108 27 1143 12 1107 28 1143 13 1113 29 N/A l 14 1119 30 N/A I 15 1121 31 N/A 16 1112 l
+
4 1
l l
l
,o . , .
+
. OPERATING DATA REPORT DOCKET NO. 50-327 DATE 03/02/95 COMPLETED BY T. J. Hollomon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l
- 1. Unit Name: Seavovah Unit One l l
- 2. Re, m Ung Period: February 1995 l [
- 3. Licensel Thermal Power (MWt): 3411.0 l l
- 4. Namepiste Rating (Gross Hde): 1220.6 l l
- 5. Design Electrical Rating (Net MWe): 1148.0 l l
- 6. Maximum Dependable Capacity (Gross MWe): 1151.0 ___ l l
- 7. Maximum Dependable Capacity (Net HWe): 1111.0 l !
- 8. If Ct.anges Occur in Capacity Ratings (Item Numbers 3 Through 7) $1nce 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 672 1.416 119.785
- 12. Number of Hours Reactor Was Critical 546.4 1.290.4 63.340
- 13. Reactor Reserve Shutdown Hours C 0 0
- 14. Hours Generator On-Line 546.2 1.290.2 61.894.5
- 15. Unit Reserve Shutdown Hours 0 0 0 ,___
- 16. Gross Thermal Energy Generated (MWH) 1.837.960.3 4.371.863.7 .20116; 860
- 17. Gross Electrical Energy Generated (MWH) _ 639.850 1.524.710 68.575.594
- 18. Net Electrical Energy Generated (MWH) 616.194 1.473.880 65.737.293
- 19. Unit Service Factor 81.3 91.1 51.7 -
- 20. Unit Availability Factor 81.3 91.1 51.7
- 21. Unit Capacity Factor (Using MDC Net) 82.5 93.7 49.4
- 22. Unit Capacity Factor (Using DER Net) 79,9 90.7 47.8
- 23. Unit Forced Outage Rate 18.7 8.9 36.2
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Chut Down At End Of Report Period, Estimated Date of Startup:
l l
\
- 0 l' * [ . .
f- +. -
OPERATING DATA' REPORT- ,
DOCKET NO. 50-328
[m DATE= 03/02/95 COMPLETED BY T. J. Hollomon TELEPHONE -(615) 843-7528 3 OPERATING STATUS.
l Notes l '
- 1. Unit Name: Seauovah Unit Two -l l
- 2. Reporting Period: February 1995 l -l
. 3. Licensed Thermal Power (MWt): 3411.0 l l-
- 4. Nameplate Rating (Gross MWe): 1220.6 l l- ;
-S. Design Electrical Rating (Net HWe): 1148.0 l l
- 6. Maximum Dependable Capacity.(Gross MWe): 1146.0 l l i
- 7. Maximum Dependable Capacity (Net MWe): 1106.0 l I
- 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 i
, 10. Reasons For Restrictions, If Any: N/A :
l This Month Yr-to-Date Cumulative. ,
- 11. Hours in Reporting Period 672 1.416 111.745 4
- 12. Number of Hours Reac'or. Was Critical 672.0 1.393.7 65.750
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 672.0 1.354.7 64.064.4
- 15. Unit Reserve Shutdown Hours 0 0 0'
- 16. Gross Thermal Energy Generated (MWH) 2,275.606.6 4.473.893.2 202.001.356
- 17. Gross Electrical Energy Generated (MWH) 784.510 1.537.493 68.545.102 [
- 18. Not Electrical Energy Generated (MWH) 758.230 1.482.037 65.596.219
- 19. Unit Service Factor 100.0 95.7 57.3
- 20. Unit Availability Factor 100.0 95.7 57.3
- 21. Unit Capacity Factor (Using MDC Net) 102.0 94.6 53.1
- 22. Unit Capacity Factor (Using DER Net) 98.3 91.2 51.1
- 23. Unit Forced Outage Rate 0.0 ' 4.3 34.7'
- 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:
1 1
- " ' - n __.-
DOCKET NO: 50-327 UNIT SHUTE 0WNS AND POWER REDGCTIONS UNIT NAME: One
- DAYE: 03/03/95 REPORT MONTH: Febru a ry 1995 COMPLETED BY:1. J. Hollomon .
TELEPHONE:(615) 843-7528' Method of Licensee Cause and Corrective -
Duration Shutting Down Event System Compgnent Action to j No. Date Type l
(Hours) Reason 2 Reactor 3 Report No. Code # Code Prevent Recurrence 1 950223 F 125.8 A 1 50-327/95002 AB N/A At approximately 1600 EST, with the reactor operating at 100 percent power. Unit 1 experienced an RCS leak at a compression fitting on a i RVLIS line in the incore instrument room. This event was initiated by i a failed compression fitting on the
- RVLIS. An inspection of the fitting and tubing indicated that the tubing pulled out of the tee.
The ferrule remained inside the nut attached to the compression tee.
The force required to remove the nut was less than expected indi-cating that the compression fitting was not aroperly assembled. The failed fitting was repaired.
Approximately 450 fittings were '
inspected; approximately 151 indetenminate fittings were identi-fled. Thirty-nine of the 151 indeterminate fittings were dis-assembled and found to be properly install ed. Therefore, a high level of confidence exists in the reli-ability of the compression fitting joints at Sequoyah. A long-term action plan for the inspection of other systems.and the Unit 2 fittings will be determined.
Fittings that were determined to have incorrectly installed ferrules were corrected as appropriate.
2 Reason: 3 #Exhibit G-Instructions I:F Forced Method:
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Mairtenance 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 Trainica and License Examination 5-Reduction F-Administrative 9-Other 5
G-Operational Error (Explain) Exhibit I-Same Source H-Other (Explain)
DOCKET NO: '50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS - tmIT NAME: Two ;Ng *
- DATE: 03/03/95 :
REPORT M WTH: February 1995 COMPLETED BY:T. J. Hollanon. Y.' 5 TELEPHONE:(615) 843-7528 Method of Licensee Cause and Corrective =
l, Duration Shutting Down Event Systes. Action to 2 4 Compgeent No. Date Type l (Hours) Reason Reactor Report No. Code Code Prevent Recurrence i
There were no outages or power -
reductions of greater than 20 percent to repcrt during February.
?
s I:F Forced 2 Reason: 3 Method: #Exhibit G-Instructions 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 Continuation of Existing Outage (NOREG-1072)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other 5 Exhibit G-Operational Error (Explain) I-Same Source
~
H-Other (Explain) >
e
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