ML20077C418
| ML20077C418 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/30/1991 |
| From: | Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105210402 | |
| Download: ML20077C418 (12) | |
Text
{{#Wiki_filter:- - --- _ - . Irrassee VW% A#wy.1101 Marset Meet Chesaga Nwssee 3NR May 15, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D.C. 20555 Gentlemen: In the Mstter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 P SEQUOYAH NUCLEAR PLANT (SQN) - APRIL 1991 MONTHLY OPERATING REPC3T Enclosed is the April 1991 Monthly Operating Report as reauired by SQN Technical Specific. tion 6.9.1.1.0. If you have any questions concerning this matter, please call M. A. Cooper at (615) 843-8422. Very truly yours, TENNESSEE V LLEY AUTHORITY p 4 E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosure
-cc: See page 2 PD 2 910430 N ffK05000327 PDR
_ _ . -. .. . . . . . . _ _ _ . _ _ _ _ _ . . . - . _ . _ _ _ . . . -. ._m. m._m.._m__ ..
'4
. i
.. l 2
'J.S. Nuclear Regulatory Commission Uby.15. 1991 '
cc (Enclosure):= 1 Mr. D. E..LaBarge,' Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 INPO Records Center Institute of Nuclear Power Opern:. ions 1100 Circle 75 Parkway, Suite-1500 Atlanta, Georgia 30389 Mr. Ted Marston. Director
-Electric Power Research Institute P.O.-B,x 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'Enforcemetit l_ Region II-
- l. 101 Marietta Street, NW, Suite 2900 Atlanta,' Georgia 30323 y ,Mr. B. A. Wilson. Project Chief U.S. Nuclear Regulatory Commission i Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
-Mr. Fred Yost, Director. Research Services-
' Utility Data Institute.
1700 K Street,-NW, Suite 400. Washington. D.C..:20006 l L w r$.
IENSSEEVAllEYAUTHORIIY NUCLEARPOWERGROUP SEQUOYAHNUCLEARPIANI
)l0NIHlYOPERATINGREPMI 10IHE NUCLEAR REGULAIORY C0)DlISSION APRIL 1991 UNII1 DOCKEI hEBER 50-327 LICENSEhEBERDPR-77 UNII2 DOCKEI hEBER 50-328 LICENSE hEBER DPR-79 ii
l OPERATIONAL
SUMMARY
q APRIL 1991 l
\
l UNIT 1 Unit 1 generated 838,840 MWh (gross) electrical power during April, with a capacity factor of 100.4 percent. On April 5, 1991, at 1018 Eastern standard time (EST), a load decrease was initiated to allow maintenance on the No. 3 heater drain tank level control valve (LCV) 1-LCV-6-106B. At 1046 EST, the load decrease was terminated and reactor power level was held at approximately 98 percent. The valve stem on the LCV had twisted when the stem block became loose as a result of vibration. The valve stem was placed in its cortret-positien and the block was tightened. At 1110 EST, power increase was initiated, and Unit I was operating at 100 percent reactor power level at 1200 EST on April 5, 1991. On April 14, 1991, at 0001 Eastern daylight time (EDT) with Unit 1 operating at 100 percent reactor power, the B-2 heater string of the condensate system ' isolated on high level. The main feed pump (MFP) low net positive suction head (NPSH) alarm was received. .A load reduction was init!ated to recover the MFP NFSH. At 0027 EDT,- the MFPs were returned to autoeatic. The low MFP NPSH alarm cleared. At_0316 EDT, B-2 heater string was back ie. service and power increase was initiated. The exact cause of the isolatlan could not be determined. Unit 1 was operating at 100 percent-reactor power at 0725 EDT on April 14, 1991. On April 20, 1991, at 1350 EDT, with Unit 1 operating at 100 percent reactor power, the B-2 heater string isolated on high level because of the faulty positioner of 1-LCV-6-43. The unit load was dropped slow *.y to keep MFP NPSH low alarm cleared. At 1420 EDT, Unit I was stable at 98 percent reactor power. Load was increased to 100 percent power following the replacement of 1-LCV-6-43 positionet . Unit i reached 100 percent power at 0120 EDT on April 21, 1991, and continued to operate at approximately 100 percent power l through the end of the. month. UNIT 2 Unit 2 generated 836,460 FNh (gross) electrical power during April with a capacity factor-of 100.1 percent. On April 22, 1991, at 1250 EDT, power was decreased to 97 percent for the performance of System Operating Instruction (50I)-47.4, " Steam Inlet Valve Testing." At-1503 EDT, the_SOI was completed '
-and load increase was initiated. At 1608 EDT Unit 2 was again operating at .
approximately 100 percent power and continued to operate at that level through the end ofcthe month.
l l
]
2-POWER OPERATED RELIEF VALVES (PORV) AND SAFETY VALVES
SUMMARY
There were no challenges to PORVs or safety valves in April. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during April. e
4
. a a
AVERAGEDAllYUNIIPOWERLEVEL , i DOCKET No. 50-327 UNIT No.- One DATE: 05-06-91 COMPLETED BY:- T. J. Ho11omon TELEPHONE: {615) 843-7528 : MONTH: APRIL 1991 ; AVERAGE-DAILY POWER LEVEL AVERAGE DnILY POWER 1EVEL DAY (MWe-Net) DAY (MWe-Net) 1 1139 17 1132 2 1138 18 1132 3 1138' 19 1132 4 1137 20 1123 5 1134 21 1131 6 1134 22 1131 r 7 1134 23 1132 8 1133 24 1132 9 1133 25 1132 10 1132 26 -1132 11 1132 27 1131- - 12 1132 28 1130 l 13- 1131 29 1128
- j. 14 1129 30 1128 15- 1l32 31 N/A' l
1 16 1131 I. l i. s
. - - _ _ , ~ . .. . - , . . - . - . . . - - . . - . . . ~ . - . - . ~ . . _ ~ - . . _ . - . . .
[ i
'I AVERAGEDAILYUNITPOWERLEVEL DOCKET NO. 50-328 UNIT No. Two DATE: 05-06-91 COMPLETED BY: T. J. Hollomon TELEPHONE: 1615) 843-7528 f MONTH: A,PRIL 1991 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY _ (MWe-Net) DAY (MWe-Net) 1 1130 17 1123 2 1129 18 _ _ , ,
1124 3 1128 19 1122 4 1127 20 1123 5- 1127 21 1123 6 1127 22 1123 7 1127 23 1126 8 1126 .24 1125'
;9 1127- 25 -1124
.10 1127 26 1124 111 1126' 27 1123- _
12 1123 28 1122 13 112!-
! 29 1122-l 14 1125 30 1122 15 1125 31 N/A-16 1127 l
l-l l
,, , . .. - . . .- - - ~ - - - ~ . . ~ _ . -. . - . . - _ - - - ~ _ . . - - . - -. . . _ . - ~
3 w OPERATiHG DATA REPORT DO:KET_N0. _id:3s? . DATE _ guy 6. 1991 C3MPtEMD BY J.Atiollomon . TELErHONE Lil$_L143-7528 QPE?ATING STATUS . , l Notes l ;
- 1. Unit Name: SeaupJAh Unit One l l 2 Reporting Perica: ,_foriT 1991 l l i
- 3. licensed Thermal Pewer (MWt): 3411.0 l l .
- 4. ' Nameplate Rating ;6rsts MWe): 1220.6 l l
- 5. Design Electrical Rating (Net MWe): 1148.0 l l
- 6. Ma'ximum Dependable Capacity (Gross MWe): 1162.0 l l
- 7. Manie.um Dependaole Capacity (Net MWe): 1122.0 l 1
- 8. If Changes Occur in Capacity Ratings iltems Number 3 Thraugh 7) Since Last Report. Give Reasons:
J- '9. Power Level To Which Restricted. If Any (Net MWe)! ___ti/6
- 10. Reasons for Restrictions. If.' Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours'in Reporting Period 719 2.879 86.184
- 12. Number of Hours Reactor Was Critical 719.00 2J748.3 42.820
- 13. Reactor Reserve Shatdown Hours 0 0 0
- 14. Pours Generator On-Line 719.0 2.729.3_ 41.825.3
-:15. Unit Reserve Shutdown Hours 0.0 ___ 0 0
'16. Gross Therma] Energy Generated (MWH) 2.451.938.6 9.210.301.2 136.496.369
' .17. Gross Electrical: Energy Genereted (MWH) 838.840 3.150.232__._ 46.21g 814
- 18. Net Electrical Energy Generated (MWH) 810.679 __ 3.039.622 44.336.498
- 19. Unit Service factor-100.0 .
94.8 48.5
- 20. Unit Availability Factor 10 0 . Q____. - 94.8 41,5_ .
l . 21. Unit Capacity Factor (Using MDC Net) 100.5 __, 94.1. 45 jl__ l 22. Unit Capacity factor (Using DER Net) 98.2 92.0 44.3__ l- 23. Unit Forced Outage Rate 0.0 5.2 43.Z__
- 24. Shutdowns Scheduled Over Next'6 Months (Type. Date, and Duration of Each):
Unit 1 Cvele 5 refuelino Sutage is scheouled to'becin October 4 1991. with a scheduled j L du'raticg_pf 60 days. i,
- 25. if Shut Down At End Of Report Pertad. Estimated Date of Startup: 'N/A I
n i l s
. . . . - - -r, . , , w ,--.e ,,r ,--en. e - --N,--,,,-,,---,. ,,.,.w, , ,,
. . ~.~ . - - . . . . . . ~ . - - --. - . - . . - - - . . ~ . - - . . . . - . _ . . ~.
iis 4 N OPERAflNG DATA RE?OP.T , DOCKET NO. 50-328 DATE fay 5. 1991 _ COMPLETED BY T. J. Hollomon TELEPHONE 16151 Bd.3.,J128__ OPERATING STATUS l Notes l
- 1. U..it Name: _Seouoyah Unit Two l l
- 2. Reporting Period: Aoril 1991._ l -l
- 3. Licensed Thermal Power (MWt): 3411.0 l _l j
, 4. .N4mtplate Rating (Gross Mwe): 1220.6 ___ l l L6
- 5. Cesign Etc.:tricel Eating (Net MWe): _jlsa Q ___ l l tu Hamimur. Ospardable C.*pacity (Grcss MWe): _llhL E._. l l
- 7. Max!mtd Depen 45bie Capacity (Net MWe): _ll224 GL_ 1 1 8; If Changas e: cur in Capacity Rstings (Items Numt+r 3 7hrou9 h 7) Since last c eport, 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 p
-11._ Hours in Reporting Period 719- 2.879 78.144
'12. Number of Hours Reactor Was Critical 719.0 2.879.0 ' 43.350
- 13. Reactor Reserve Shutdown Hours 0 0 0
~14. Hours Generator On-Line. 719.0 2.842.0 42.402.4
-15. Unit Reserve Shutdown Hours- 0.0 - 0 0_
- 16. Gross Thermal Energy Generated (MWH) 2.449.233.3 9.579.232 h_: 131.853.693
.17. Gross Electrical Energy Generated (MWH) 836.460 -3.277.940' 44.766.156
- 18. Net Electrical Energy Ger4 rated (MWH) 807 952 3.163.408 _ '42.7C7./R6 19.~ Unit Service Tactor 100.0 98.7 54.3
- 20. Unit Availability Factor- _
100.0 -98.7 54.3 48.8
.21. Unit Capacity factor (Using MDC Net) 100.2 ___,
97.3,
- 22. Unit Capacity Factor (Using DER Net) 97.9 95.7_ 47.7 23.' Unit Forced Outage Rate 0.0 1.3 -38.8 2^. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): -
25.- If Shut Down At End Of Report Peri'od, Estimated Date of 'Startup: ,,N/A n .y . -n
DOEKET NO: 50-327 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: _JQne UATE:_ _Q M S/91 REPORT MONTH:J gril 1991 COMPLETED BY:L_1,_ M lgmgo IfEEPHONL:LkJAlt41.l.M Method of licensee Cause and Corrective Duration Shutting Down Event Systgm Compgnent Action to No. Date Type (Hours) Reason Reactor ~ Report No. Code Code Prevent Recurrence S 910405 F A S SJ LCV At 1018 E$f a load dec. ease was initiated to allow maintenante on 1-LCV-6-1068. At 1046 EST, the load decrease was terminated and reactor thermal power was held at apprOximately 98 percent. The valve stem on the (CV had twisted when the stem block became loose as a result of vibration. The valve stem was piaced in its correct position and the binck was tightened. At 1110 EST. a power increase was initiated. Unit I was operating at 100 percent reactor power at 1200 E$i on Aoril 5. 1991. b , 910414 l A 5 SJ RLY With Unit I operating at 100 percent reactor power, 8-2 heater string of the condensate system isolated on high level. The low Mf P NPSH alarm was received. A load reduction was initiated to recover Mf P NPSH. At 0027 EDT, the MfPs were returned to autn. The low MFP t4PSH alarm (leared. At 0316 E DT, B-2 heater string was l back in service, and power increase was initiated. Unit I was operating at 100 percent reac tor power level at 0725 EDT on April 14, 1941. E*act cause of the isolation (ouki not be r- . - - - . _ - . _ - - L I 2 Weason: 4 f: Forced 3 Method: E=hibit G-Instructions 5: 5theduled A-E qui pmen t f ailure (Emplain) 1-Manual for Preparation of Data B-Maintenance or lest 2-Manual Stram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) file D-Regulatory Restruction 4-Continuation of Existing Outage (NURtG-1022) t-Operator T raining and L icense Examination 5-keduction I-Ado.inistrative 9-Other G-Operational Error (Emplain) SEnhibit I-Same Source H-Other (Explain)
.. . =
. , . . .,. _ m W
-DOCKET NO: 60-327' . .
-UNIT NAME: One UNIT SHUTDOWNS AND POWER REDUCTIONS
'DATE: 05/08/91
! COMPLETED BY:T. J. Hoffomen: . , i kEPORT MONTH: Aoril 1991 TELEPHONE:(6151 843-7528 . Method of Licensee Cause and Carrective. :! t Duration Shutting Down- Event Systgm Compgner.f Action to Date Type -{ Hours) Rea' son2- Reactor Report No. Code ' Code ' Prevent Recurrence. - No. A 5 SJ RLY. With Unit 1 operatir.g at 10. , '7 910420: f. percent , reactor power level . B heater string isolated on high level because of the faulty positioner of 1-tCV-6 43. The j unit load was dropped slowly to I keep Mfp NpSH' alarm cleared. At , 1420 EDT, Unit I was ' stable at ' i 98 percent reactor power. Load increase to 100 percent power . was initiated following replace- )
' a.ent of 1-tCV-6 43 positioner.
Unit I reached 100 percent" power i at 0120 EDT on April 21, 1991, il dnd Continued to operate at f approximately 100 percent reactor ,; power through the end of the '; month, ; e i I i <. 1 i I i l. I i 4 Enhibit G-Instructions' -;
-I f: forced 2 Reason: 3Hethod:
A-Equipment failure (Enplain). 1-Manual for Preparation of Data S: Scheduled Entry sheets f or Licensee B-Maintenance or Test 2-Manual Scram l C-Refueling 3-Automatic Scrar. Event Report (LER) file: D-Regulatory Restruction 4-Continuation of Existing Outage (t4UREG-1022) 5-Reduction ; E-Operator Training and License Examination ' f-Administrative .. 9-Other G-Operational' Error (Explain) SExhibit I-Same Source H-Other (Explain) , i
, - .m .- .
DOCKET NOT 50-328 Two f UNIT SHUTDOWS AND POWER REDUCTIONS trJIT NAME: DATE: 03/08/91 .. REPORI NONTH: Aoril 1991 COMPLLILD BY:1 J. Hollemon ' . TE1 EPH0r4E:lb.)i)_f4M6
?
Method of Licensee . Cause and Corrective Shutting Down Event Action to Duration Systgm 'Compgnent Prevent Recurrence No. Date Type l (Hours) Reason2 Reactor Report No. Code Code SB FCV At 1250 EDT, a power decrease 3 910422 F. B 5 to 97 percent was initiated
. f or the perf ormance of 501-47.4
" Steam Inlet Valve Testing."'At 1503 EDT. the SOI was completed i and load increase was'initiatedJ At 1608 EDT, Unit 2 was op? rating ,
at approaimately 100 percent . reactor power and continued to i operate at approximately 100 . . percant poveer through the end of [ the month, i i i i 1 3 - 4 tahibit G-Instrettions j I t: forced 2 Reason:. Method: for Preparation of Data ; 5: Scheduled A-Equipment failure (fxplain) 1-Manual r 2-Manual Scram Entry sheets for Li ensee B-Maintenance or Test Event Reptet (LER) fate C-Refueling 3-Automatic Scram ; D-Regulatory Restruction 4-Continuation of Emistino Outage (NURLG-1022) E-Openator Iraining and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) SEnhibit I-Same Source ! i ti-Other (Explain)- I i i}}