ML20094D725
| ML20094D725 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1991 |
| From: | Hollomon T, Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9112240007 | |
| Download: ML20094D725 (10) | |
Text
m-i W
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A un m m, as-% r - c-1 m
Jack L Wdson
- r 2,m r,
December 16, 1991 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) - NOVEMBER 1991 MONTHLY OPERATING REPORT Enclosed is the November 1991 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, l}
rtH
.1/ L. Wilson Enclosure ec:
See page 2 9112240007 911130 PDR ADOCK 05000327 P
R PDR
/
I
U.S. Nuclear Regulatory Commission Page 2 December 16, 1991 cc (Enclosure):
INP0 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission y
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Ted Marston, Director Electric 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 Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 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, NW, Suite 400 Washington, D.C.
20006
- 3..
TENNESSEE VAIJEY AUTHORITY-NUCIEAR POWER CROUP SEQUOYAH NUCLFAR FIANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGUIAIDRY C0fMISSION HRYRtBER 1991
' UNIT 1 90CKET NIMBER 50-327 LICENSE NIMBER DPR-/7 UNIT 2 DOCKET NUMBER 50-328 LICMSE NIMBER DPR-79 t;
a OPERATIONAL
SUMMARY
' NOVEMBER-1991 11HIL1 Unit 1' entered the Cycle 5 refueling outage on October 5, 1991. At'the beginning of November, Unit I was in Mode 6 (defueled).
On November 4, 1991, fuel movement began to reload the core and was completed on November 7, 1991.
Unit 1 entered Mode 5 on November 14,_1991, at 2018 Eastern standard time (EST) and remtined in Mode 5 through the end of November.
11 NIL 2 Unit 2 generated 530,950 megawatthours (MWh) (gross)' electrical power during November with a capacity factor of 63.46 percent. On November 7, 1991, at 1403 EST, Unit 2 reactor tripped on low-low steam generator level resulting from an inadvertent main steam isolation valve closure.- On November 7, 1991, it was determined that various 480-volt (V) electrical boards did not have selective coordination between the feeder breakers and the load breakers on the boards as a result of a breaker design feature.
On November 8, 1991, at 0056 EST, the 480-V Shutdown Board 1B2-B was inadvertently short circuited by electricians during activities to correct the breaber coordination problem resulting in a trip of the board. Unit 2 entered Mode 5 on November 8, 1991, at 2002 EST to repair the shutdown board and complete the modifications to correct the coordination problem.
On November 14, 1991, 480-V Shutdown Board 1B2-B was repaired, and the breaker modifications were completed. At 0454 EST on November 15, 1991, Unit 2 entered Mode 4 and was again online on November 17, 1991, at 1417 EST.
Unit 2 we.s operating at 100 percent reactor power level again on November 19, 1991, at 1233 EST.
EQWER-OPERATED RELIEF VALVES (PORV) AND__ SAFETY VALVES _EM]A]W
-There were no challenges to PORVs or safety valves in November.
.0EEEIIE_ DOSE _CALCHIATION MANUAL (ODCM) CHANGES
-There were no changes to the ODCM during November.
1 AVERACE DAILY UNIT POWER IIVEL DOCKET NO.
50-327 UN1r No. _One DATE: _12-Qh-SL COMPLETED BY: L J. linilomon TELEPHONE: 1615).841-1528 MONTil: MQV MDER 1991 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL 11AI R Ee:Netl_
DAY (MWe:Het )--
1
-2 17
-2 2
-2 18
-2 3
-2 19
-2 1
4
-2 20
-2 5
-1 21
-2 6
-6 22
-2 7
-4 23
-1 8
-5 24
-1 9
-6 25
-2 10
-4 26
-2 11
-5 27
-1 12
-5 28
-2 13
-7 29
,-2 14
-5 30
-1 15
-5 31
_. _.N A 16
-5
.4 AVERACE DAILY UNIT POWER LEVEL DOCKET NO.
50-328 UNIT No.
Two DATE: _12-04-21 COMPLETED BY:
L_ Ji_Rollomon TELEPl!ONE:
Ihll)_Sh3-2 28
- MONTil: 110VEtiBEA.1231 AVERAGE DAILY POWER LEVEL AVERAGE DAILY PuWER IEVEL DAY IMWe-let)
DAY INde-NeL) 1 IL17 17 (13 2
1117 18 426 _
3 1118 19 1089 a
1119 20 1114 5
1119 21 1119 6
1120 22 1122 7
631 23 1122_
8
-28 24 1122 9
-26 25 1J 23 10
-16 26 1122 11-27 1123 12
-16 28 112!t_
13
-21 29 Il23 14
-20 30 1123 15
-37 31 NA
- 16
-35
OPERATING DATA REPORT DOCKET NO.
_h0.22L_
DATE _De q1.fu_1911_
COHrLETED BY Im.lullollomort._
TELEPHONE ltELS41_]$1$_
QEfl#1tCL11AlV5
_ _ _l Notes l
1.
Unit Hame:,_leguayah_VojLQne l
l 2.
Reporting Period: _flotembeL1931 l
l 3.
Licensed Thermal Power (HWt): 3411.Q l
l 4.
Nameplate Rating (Gross HWe): _1220J l
l
~
5, Design Electrical Rating (Het HWe): _1140,0 l
l 6.
tiaximum Dependable Capacity (Gross tNe):.llbla.
l l
7.
Maximum Dependable Capacity (Het tNc):._JJ 2210 j
_l 8.
If Changes Dccur in Capacity Ratings (Item Humbers 3 Through 7) Since Last Report, Give Reasons?
I 9.
Power Level To Which Restricted, If Any (Net HWe): __N/A
- 10. Reasons Fo Restrictions, If Any:
fl./A t
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 72D__
8 J1ft__
SjJZj
- 12. Number of Hours Reactor Was Critical DJ 6,533 1 4L591
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line Q,0 L591 1 45496.1
- 15. Unit Reserve Shutdown Hours 0.L__
p_
_D
- 16. Gross Thermal Energy Generated (HWH) 02 0
_2L11L31LQ_
1_4L93L19_1__
- 17. Gross Electrical Energy Generated (HWH) 0 7.340.31Q__
_.50,4JBJ16 18, Net Electrical Energy Generated (HWH)
(2,2 11) 7.086.158 JS23J14_. _
- 19. Unit Service factor O0 B l.1 49.9 t
- 20. Unit Availability Factor 0.D_ __
Q1 1 49.9 _
- 21. Unit Capacity Factor (Using HDC Net)
-QJ _ _
18 1 4L2_
- 22. Unit Capacity Factor (Using DER Het)
-01._.
7 7. Q,.,
45.,1_
- 23. Unit forced Outage Rate DJ_
21, 4 L6_.
- 24. Shutdowns Scheduled Over Hext 6 Honths (Type Date, and Curation of Each):
,_ _ Unit 1 Cnit.1 rtive11ngJutage_htg60_.011sb.en_5ml2R_at_0249_110lb _.Gentrator syuihranjutj_o_n is scheduled _fnLDatteher__lii_.192h_
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: __.Decemhet.lf,1991
.3
-s
}~
OPERATING DATA REPORT DOCKET NO. _19-326 DATE _Det. 4. 1991 COMPLETED BY T. J. Hol l otDn_
TELEPHONE (615) 843-7$2B__
s
-QPERATING STATUS l Notes l
1.
Unit Name: __itau2yph Unit IM2.
l l
2.
Reporting Period: November 1991 l
l 3..
LicenseJ The yal Power (HWt): _331120 l
l 4.
Nameplate Rating (Gross tNe): 1220.5 l
l
~
5.
Design Electrical Rating (Net HWe): 1148.0 l
l 6.
Hasimum Dependable Capacity (Gross HWe)1 _116Z.0 l
l 7.
Maxir.n Dependable Capacity (Not HWe): _1J22.0 j
l 8.
If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 9.
Power tevel to Which Restricted, If Any (Net HWe):
N/A
- 10. Reasons for Restrictions, If Any:
PMA This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 8.016 83.281
- 12. Number of Hours Reactor Was Critical d97.1 7.793.1 48.264
- 13. Reactor Reserve Shutdown Hours 0
0 0 _
- 14. Hours Generator On-Line 479.8 7.738.8 47.299.2
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross Thermal Energy Generated (MWH)
_11567.576.9' 26.154.023.4 148.428.474
- 17. Gross Electrical Energy Generated (HWH) 530.950 8.819.465
__502307.601
- 18. Net Electrical Energy Generated (Hel)
__10$ R 2
,_ 1 499.857 48.125.935
- 19. Unit Service Factor 66.6 96.6 56.8 20, Unit Availability Factor 66.6 26,1 _
56.8_
~ 21. Unit. Capacity Factor (Using HDC Net) 62.6 94.5 51.5
- 22. Unit Capacity factor (Using DER het) 6J22___
92.4 50,3__
- 23. Unit Forced Outage Rate 33.4 3.5 36.4
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
~
Unf t 2 Cycle 5 refuelino outaae is scheduled to beoin March 13. 1992. and is currently scheduled as a 60-day outaoe.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
N/A f
COCCIET NO:
- S0-227 UNIT SKUTDOWHS AND POWER REDUCTIONS UNIT NAME:
One DATE:
12/04/91 REPORT NOMTH: Novesber 19"1 C0t4PLETED BY:T_'.t. Holletnan TELEPHONE:I6157 843-7528 Method of Licensee 1
Cause and Corrective.
Duration Shutting.Down-Event System n Component Action to l
2 5
d b
No.
Date' Type (Hours)
Reason Reactor Report No.
Code Code Prevent Recurrence 1
9 911005 5
720.0 C
1 Unit 1 Cycle 5 refueling outage continues.
I: Forced Reason; hthod:
2 F
Exhibit G-Instructions S: Scheduled A-Eauipent Failure (Explain) 1-Manual for Preparatica of Data B-Haintenance 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 Training and License Examination 5 Deduction F-Adminis trati ve 9mher S
G-Operational Error (Explain)
Exhibit I-Same Source H-Other (Explain)
.y
?
OCEKET NO:
50-320 0'
UNIT SHUTDOWS AND POWER REDUCTIONS
- UNIT NAME:
Two DATE:,
?2/04/91 REPORT MONTH: November 1991 COMPLETED BY:T. J7 Hollomon TELEPHONE:1615) 843-752s Method of Licensee Cause and Corrective.
Duration Shutting Down Event System Component Action to I
2 3
b No.
Date Type (Hours)
~ Reason Reactor Report No.
Code #
Code Prevent Recurrence 5
911107 F
240.2 A
3 50-328/91006 SB 15V On 11/7/91, at 1403 EST, Unit 2 50-327/91026 ED BKR reactor tripped on low-low steam generator level resulting from an inadvertent main steam isolation valve closure. On 11/7/91, it was determined that various 480-V electrical boards did not have selective coordination between the feeder breakers and the load breakers on the boards as a result of a breaker design feature. On 11/8/91, at 0056 EST, the 480-V Shutdown Board 182-8 was inadvertently short circuited by electricians during activities to correct the breaker coordination problem resulting in a trip on the boa rd. Unit 2 entered Mode 5 on 11/B/91, at 2002 EST to repair the shutdown board and complete the nodifications to correct the coordination problem. On 11/14/91, 480-V Shutdown Board 182-8 was repaired, and the breaker modifications were completed. At 0454 EST on 11/15/91 Unit 2 entered Mode 4 and was again online on 11/17/91, at 1417 EST. Unit 2 was operating at 100% reactor power level again on 11/19/91 at 1233 EST.
I I
2 3
F: Forced Reason:
Hethod:
Exhibit G-Instructions
$: Scheduled A-Equipment railure (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 (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other S
G-Operational Error (Explain)
Exhibit I-Same Source H-Other (Explain)
-