ML20101T686
| ML20101T686 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1992 |
| From: | Hollomon T, Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9207210328 | |
| Download: ML20101T686 (10) | |
Text
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- J L W han vwwa.:nt Sarnen twmx na n July 15, 1992 U.S. Nuclear Regulatory Commission AT'IN Document Control Desk Washington, D.C. 20555 Gentlemen:
L-In-the Matter cf
)
Docket Ncn. 50-327 Tennessee Valley Authority
)
50-328
- SEQUOYAll NUCLEAR PIANT (SQN) - JUNE 1992 MONTilLY OPERATING REPORT Enclosed is the June 1992 Monthly Operating Report as required by SQtt Technical Epecification 6.9.1.10.
If you have any questions cencerning this matter, please call M. A.' Uooper at (615) 843-8924 Sincerely.
l
- s WLOJsn L. Wilson Enclosure
- cci-See page 2
? Y G n.t n f
9207210328'920630'
- PER ADDCK'05000327
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U.S. Nuclear Regulatory Commissions Pago 2 July 15, 1992 cc (Enclosure):
'INPO Records Center Institute of Nuclear Power Operations i
1100 circle 75 Parkway Suite 1500 Atlanta, Georgia 30339 Mr. D. E.14 Barge, Project Manager U.S. Nuclear Regulatory Commission 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-r
-2600 Igou Ferry Road-
-Soddy-Daisy Tennessee 37379 Regional-Administration U.S. Nuclear Regulatory Commission Office of Ineraction.and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia. 30323 l.
!r. b. A.-Wilson, Project Chief M
U.S. Nuclear Regulatory Commission Pegion.II 101-Marietta. Street,-NW, Suite 2900 Atlanta, Georgia 30323 Mr. F. Yoat, Director Research Services
-Utility Data Institute
'1700 K Street, NW, Suite 400
-Washington, D.C. 20006 L
TFRNRSSEE VAIJ.EY AUTil0RITY NUCl#At POWER GROUP SEQUOYAll NUClfAR FIANT MONTill.Y O/ERATING REPORT TO Tile NUC1 EAR REGUIAftlRY C0fMISS10N JUNE.1992 UNIT 1 DOCKET NIMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 IX)CKMT NIMBFJ 50-328 LICENSE NIMBlut DPR-79
OPERATIOdAL StM1ARY JUNE 1992 UNIT 1 L
Unit 1 generated 837,380 megawatthours (tNh) (gross) electrical power during June, with a capacity tactor of 99.95 percent. Unit i operated at near 100 percent reactor power throughout the month of June.
UMll_2 Unit 2 generated 785,324 megawatthours (tNh) (gross) electrical power during June, with a capacity factor of 93.74 percent.
On June 27 at 0953 central daylight-time (CDT), a Unit 2 reactor trip occurred from en over temperature (OT) delta T reactor trip circuit. The Loop 1 i
- reactor coolant system delta T channel was out of service for maintenance activities.
The Loop-3 cold-leg resistance temperature detector failed low, resulting in Loop 3 OT delta T bistables actuations therefore, comple'ing the reactor protection system two-out-of-four logic to initiate a reactor trip.
l Unit 2 tied online again on June 28 at 1241 CDT, and reached 100 percent l
reactor power on June 29 at 1800 CDT. Unit 2 continued to operate at l-
~100 percent reactor power through the end of June.
F.0WER-DIEPAIED_.RELIEE_VALVIL.(f.0RValELSAEEILVALVES SVt21ARY There were no challenges to PORVs or safety valv.ts in June.
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AVEAACE DAILY UNIT POWER LEVEL DOCKET NO.
._1Q-327-UNIT No.
One DATE:
02-fS _92 COMPLETED BY T J J 011cman TELEP110NE: Ihh]_B!t3._2328 MONTil JWiE.1992_
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (tMe-Nel).
DAY (MWe-Neit 1
-lus 17 1124 4
2 1135 18 1126 3
1 13S 19 lill._
t 4
.113/L. _, -
20
_1124._
5
_lllk 21
[125 6
1131 22
_112It 7
__1131 23 112.6 8
113.Q.
24 1123 9
1129 25 112.2 10 1128 26 1119 11 ll25 27 1118 12
,_1125.
28 1116 13 ll22 29 1118.
14 1122_
30 111.8 1.
15
.112/
31
![/A.
_1127 16 l
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r
['
F AVERACE inAILY UNIT PINER LEVEL DOCKET NO.
.JQ_328 LHIT No. __Tw.o__
DATE: _01.EE-2 J
CT!PLETED BY: T A llo11omon TELEP110NE
{611)_.Bh3-1528 i
MONTH:
JUNL.1292_.
j I
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL UAY ItIWerNcLL DAY DNe-find 1-
' 1131 17 112L 2
1131 18 1113 4
3 1130 19 1122 _.-.
4 1133__
20 1121 5
_.1126_
21
_.1122 _.
6 1129 22 ll21.
7-1129 23 1123 8
_1129-24
.1124 9
1127 25 1120 10' 112L 26 1119 11
_ 1116 27 skL_
12 112E 28 93 13
.1125.__
29 91_._._.
6.
14
_1125 30 111 1 15 L126 31 Ji/ L 16
_11 23 l
OPERATING DATA REP 0kT DOCKET No. _10:32L___
DATE h ly_S 1932__
COMPLETED DY 11_L_tiglMog,,
TELEPHONE {$_11L.DA3:1$ZQ l
Of1RA11t!G 11A1U3 l Notes l
I 1.
Un(t Name: _ itgugnh,.UnlLQat.
l l
2.
Reporting Period: hat 1992 l
l 3.
Licensed.Therinal Power (HWt): _3411.0 l
l 4.
Nameplate hting (Gross HWe): _lZZQ16 l
l S.
Design Electrical Rating (Het HWe): 114fl.0 l
l
_6. Maximum Depandable Capact ty (Gross ifde): 11f2 d _
l l
E
- 7. _ W.ximum Dependable Capacity -(Het HWe): 112LQ l_.-- --
1 Bi If Changes Occur in Capa:lty Ratings (Item Nue. vers 3 Through 7) Since Last Report, Give Reasons:
- 9. -' Power level To Volch Restricted, If Any (Net IMe):
N/A
- 10. Reasons Fer Restrictions, if Any:
N/A This Month Yr to-Date Cumulative I'
11., Hours in Reporting Perioda 721 4. 3 6.B__
95,433,_._
.12. Number of Hours Reactor Was Critical-72L_Q 1$3.Q.d 5L464
- 13. Reactor. Reserve $hutdown 16urs g
o.
0_
- 14. Hours Generator On-Line
._12L O 3.436 ft.
49.351.d 15 - Unit Reserve Shutdown Hours -
020
.__.Q_
Q_
.16. Gross Theimal Energ) Generated (!!WH) 2.455 321,2 11.d20.,495.1..
16LQQLQ28
- 17. Gross Electrical Energy Generated I,HWH) 837 380
.. 3 83a.558 _,_54J00 054 _
.18." flet Electrical ?.nergy Generated (HWH).
60?d99
_L6BS. 643.....
- 52. 253. 37L._._
- 19. Unit Service Factor
.1Qho
'lho._
.51.2
- 20. Unit' Availability factor 100.0 79 6 51.2-
-r
-21.= Unit' Capacity raetor (Using HDC Net) =
1%#._
13_.
.48 J._,
22.-UnlU Capacity factor (Using DER Net)-
97.8 72d 4L1_.
- 23. Unit f orced Ostage Rate; 0,.0 20,L 4.q. 4 4
~
'24. ShJtdowns Scheduled Over Next 6 Months (Type. Dete, and Duration of Each):
25.IfShutDownItEnd_0fPeportFeriod:EstimatedDateofStartup:
~
)
4
- - -. - -. -. - - ~. -
. - ~
OPERATING DATA REPORT DOCK (i NO. _$Q-32B DA1C M y 0 J 292.
COMPLETED BV L_1_1[Qllpan0__
TELEPHONE 16L$LBj3 ]i?L DECM11!iG 11 AIMS l Notes l
1.
Unit dame: _$tavnyA!LDaiLIro_
l l
l 2.
Reporting Feriod! _ lune.1992 l
l 3.
Licensed Thermal Power (HWt): _1411.0
.l l
4.-
Nameplate Rating (Gross HWe): _1220$_
l l
1.
5.
Design Electrical Rating (Net HWe): _1141 0 l
l
- 6..Haximum Dependable Capacity (Gross HWe): 1162J.__
l l
7.
Maximum Depend 4ble Capacity (Net HWe): _1127,.0 l
l S.
If Changes Occur in Capacity. Ratings (Item Numbers 3 Thhugh 7) Since Last Report. Give Reasons:
~
9.
Power Level To Which Restricted, If Any (Net NWe):
N/A
- 10. Reasons For Restrictions.. *f Any tyA l
This Month Yr-to-Date Cumulative II. Hours in Reporting Period' 7?1 4.368 88 393 2
1~2. Number of Hours Reactor Was Critical 701.Q._._
2 J,23 d..
51.3J2
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-l.ine__
694 2 2.744.3 iQ2281 L -
15.. Unit Reserve' Shutdowii Hosts LO 0-0
- 16. Gross Thermal Energy Generated (MdH)
,_Zd11.007. 7
,,_L3ALJABA J59aZ6L151
- 17. Gross Electricai Energy.enerated (HWH)
_,_11 0 324
,_2JJ3432q_.,_
_.53JjtL611 l
l:
-18. Net Electrical Energy Generated (HWH)-
757.195 2.70Lff!L. _5.L651404 L
- 19. Unit Service Factor 9L3 _
6LB.,
SIJ_
'20. Unit Availability Factor 9L3__._
6La_
57,d__
- 21. Unit' Capacity-Factor _ (Using HDr. Net)-
.9L6 55.3 S L,1__
- 72. ' Unit Capacity Factor (Using DER Net) 91 1 Sg A
$L9_
23.' Unit Fori.ed Ov' age Rate 3.7
_ _2d_,
3hL
- 24. Shutdowns Scheduled Over Newt 6 Honths (Type, Date, and Duration of Each):
l j-
- 25. 'If Shut Down At End Of Report Period. Estimated Date of.Startup:
p a wL
DOCFET MO:
cf-227 UNIT SHUTDOWNS AhD POCR REDUCTIONS
.(MIT NAPE:
we -
DATE:
07/0*/92___
REPORT MONTH: JUNE 1992 CONPLETED BY:1, J. Hqligw;n TELEPHONE:f6151 S43-75El Cat:se and Cerrective l System j
Pethod of Licensee l
Cog onent Action to l Duration Shut *ing Dcwn Event I
2 3
5 8
No.
Date Type (Hours)
Reason Reactor Report No.
Code Code Prewt Recurrence 1
No activities to report this period.
I I
I 2
3 kxhibitG-Instructions Method:
I: Forced Reason:
F 1-Msnual for Preparation of D*ta 5: Scheduled
,bEquipment Failure (D plain)
B-Maintenance or Test 2-Manual Scram Entry sheets fer Eicer.see 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continuation of Existing Outage (NUREG-1022)
D-Regulatory Restruction E-Operator Training and License Examination 5-Reduction F-Admini strati ve 9-Cther SExhibit I-Same Source G-Operational Error (Explain)
H-Other (Explain)
z _ _ _ _ _ _ _ _ _ _
t 2
COCKET NO:
50-328 1MIT SKUtDOWNS AND POWER REEUCTIONS (HIT NAME:
- Tm.-
DATE:
07/03/92 REPORT MONTH: Jane inC?
COMPLETED BY:T. J. t*eilosen TELEPHONE:f6151 843-798-l Y
Method of Licensee Cause and Corrective Duration Shutting Down-Event System Component Actica to l
2' 3
d 5
No.'
Date IType l(Hou-s)
Reason Reactor R*pertNo.-l Code Code P
L' Recurrence c
1 4
-920627
-F' 26.8 A-3 328/92008-JG PEN At 0953 CDT. Unit 2 teact I
tripped free 100 percent,awer.
l The trip was the result of a t
coincident (2/4) logic betwem L
Ltop 1 and 3 over temperature delta T prctection. Loep 1 delta T/Tevg charnel bad been removed free service at 0236 CDT because of spurious ala*ms and l
indication. The protection t
bistables were placed in manual 3
trip when the loop was rmved
,i free service for maintenance i
4 activities. The second channel.
I Loop 3. coinciceetly failed low.
resulting in completion of the i
i.
reactor protection system logic.
initiating a reactor trip. The.
cause of the failure appears to have occurred as a result r.,f hich I
.esistance associated with the RTD i
penetration. The problems with the RTDs were corrected and i
returned to service.
Unit 2 tied online at 1241 CDT en 6/28/92, and reached 100 percent l
reactor pcwer at 1600 CDT on 6/29/92.
t I
l
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t j
.t I
2 3
F: Forced g,,3,,
Method:
Exhibit C-Instructions
[
4 l
5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data 1
B-Maintenance or Test 2-Manual Scram Entry sheets for. Licensee f
C-Refueling 3-Autematic Scram Event Report iLER) File
.D-Regulatory Restruction 4-Centinuation of Existing Outage (NUREG.1022)
[
E-Operator' Training and License Examination 5-Reduction I
F-Administrative 9-Other i
S G-Operational Error { Explain)
Exhibit L-Same Source
[
Mther (Explain) l l
I l
=
t F
i f
.