ML20087E854

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Monthly Operating Repts for Dec 1991 for Sequoyah Nuclear Plant
ML20087E854
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/31/1991
From: Kollomon T, Joshua Wilson
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9201220191
Download: ML20087E854 (10)


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. U.S. Nuclear Regulatory Comission Document Control Desk ATTN:

' Washington, D.C. 20555 Gentlemen:

In the Matter of' ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328-SEQUOYAH NUCLEAR PLANT (SQN) - DECEMBER 1991 MONTHLY OPERAT!NG REPORT

' Enclosed is the December 1991 honthly Operating Report as cequired by SQN Technical Specification 6.9.1.10.

Save any questions concerning this matter, please call h, -coper at -(615) 843-8924.

Sincerely, s%

J L. Wilson Enclosure cc: See page 2 I

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U.D. Nuclear Reguintory Connission Page 2

' JAW 151992 cc (Enclosure):

INPO Reconds Cen.or Institute of Nuclear Power Operations 1100 circle 75 Parkway Suite 1500 Atlanta, Cecygia 30389 Mr. D. E. Lair.rge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Ted Marston, Director Electric Pcwer Research Institute P.O. Box 10412 Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Rsad Boddy-Daisy, Tennessee 37379 Regional Administration U.S. Nucleer Regulatory Commission Office of .nspection and Enforcement Region 11 10L Harietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. B. A. Wilson, Project Chief II.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, FM, Suite 2900 Atlanta, Georgia 30323 Mr. F. 70st, Director Research Services Utility Data Institute 1700 K Street, NW, Suite 400 Wachington. D.C. 20006 x .

._____E__._____m_____________.__..__________._.m____.__. ___ .___._ _ ._.__ .- _ -

a 7100tl(88EE VAll.EY AU160R11T NUCIJAR l'0WER GROUP REQUOYAll NUCl.EAk PIANT NON11tLY OPERATING REPORT 1U TilK

. NUCIEAR REcu1AtoRY Corel!HSION 14CNMLBER_1921 l

UNIT 1 DOCKET NtMBKit 50-327 LICENSE NtMBER DPR-77 UNIT 2 DOCKET NLMBER 50-328 LICl9tSE NtMBER DPR-79 c

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. OPERATIONAL

SUMMARY

, DECEM!TR 1991 l t

UNIL1 .

-Unit 1 Cycle 5 refueling outage ended on December 20, 1991, at 0941 (Eastern Standard Time lEST)) when Unit 1 was returned to service. Unit 1 generated 198.540 megawatthours (MWh) (gross) electrical power during December with a i capacity factor of 22.97 percent. Unit I was taken of fline on incember 20, 1991, at 1750 EST for perfortnance of scheduled turbine overspeed test and was ,

returned to service at 2112 EST. Power level increase was initiated, and i Unit I was operating at approximately 98 percent power on December 28, 1991.

On December 28, 1991, at 1152 EST, Unit i experienced a turbine runback to 75 percent rated therinitt power as a result of the No. 3 heater drain tank (llDT) i pump bypara valve opening. Power level increase was initiated at 2026 EST Decetuber 28, 1991. Unit 1 was operating at approximately 98 percent reactor power level at the end of December 1991.

UNIL2 Unit 2 generated 850.610 MWh (gross) electrical power during December with a L capacity factor of 98.39 percent. On December 7. 1991, at 0434 EST, Unit 2 reactor power level was decreased from 100 percent to 82 percent because the l No. 3 HDT invel control valves were indicating full closed with erratic pump )

readings on the No. 3 HDT pumps and 0 percent level its the N. 3 IlDT. Further  !

power level decrease from 82 percent to 68 percent was initiated at 0936 EST fcer replacement of one of the level control valves. On December 8. 1991, at 1011 EST, reactor power level increase was initiated. Unit 2 was again operating at 100 percent at 1421 EST and continued to operate at 100 percent

'through the end of December.

t IDWER-Of EEAIElllEL1EE_VALVEL.( f ORV.LANESAEETLVALVES.EUMMARY  ;

There were no challenges to PORVs or safety valves in December.

DEEPlILDOSE_CALCUIATIOL.t!ANUAL_(DDCt1LCIIANGES i There were no changes to the ODCM during December.

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AVERACE DAILY ifNIT P(MER 1.EVEL DocEET No. _5 0-3 2L.__. UNIT No. - Sne DATE: _01:03-92 _ _

cotirLETED BY: I,l.._Ilo110mn TELErit0NE: (611L843-7328 MONTil DECl21BEILIPyl AVERAGE DAILY POWER LEVEL AVERAGE DA1LY FOWER LEVEL DAY _ _(HWe-Re t ) DAY -- _IMWe-Net L 1 _ -3 17 .30 _.

2 -5 18 __. ___..-33 _ _ _ ._..

3 -2 19 -33 4 -2._ _

20 _ 56 5 -2 21 248 _

6 _ _-7 22 _., .._25 L - __ .

7 _ _ _ _ _ . _ _ - -2 23 24Z_

8 - 2___. 24 . 436__ 1 9 _- 2 25 Z.13_

10 . . . -9 26 111 11 -33 27 B27 12 -28 28 92$_

13 -28. 29 _1058_

14 30 1043 15 -2fi 31 -

_1033 -_

16 _ -33

4 AVf3 TACH DAILY UNIT POWKR IJNEL DOCKET NO. _$_0-328_. ._ (fNIT No. _..Iyo DATE: .31-03-92_ _

COMPLFTED liY: L_J ._1[o11pmen TELEril0NE: H1$L66321$28 MONTili DECEMBELL.1991 AVERACE DAILY POWER LEVEL AVERAGE MILY POWER LEVEL DAY (Wedir_tJ DAY - tWe-NetJ >

1 _ 1123_ __ 17 1119_.

2 _..._._ _1123 18 _, _-_1120 3 _ _1122 19 _ _._11.21 4 __ 1122__ 20 112L.__ -

5 . _ - 1122 21 .. _ 1111__

6 _ _ 1122.__.._ - 22 J118 7 _ _ _J 70 _

23 1111 8 -__ 9 39_ - 24 _ 1121 9 1121 25 1121 10 1121_ 26 ligt 11 _._ 1120_ 27 112L 12 1121 28 _1120 13 1120 _. 29 1120 14 ilm_ 30 .1120 15 112a__ 31 _._1119__ __

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s OP[ RATING DATA RCPORY DOCK [1 NO. .

DATE .30.222 Jggd L J.,.11ol;

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99 00HPLEit0 tlY umort.

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l Notes l l

1. Unit Namel _ltguGJ AIL MalLQ0t l l  !
2. Reporting Period! .fttedet.1931 l l )
3. Licensed thermal Power (HWt)! 3d&Q. l l 4 Nameplate Rating (Gross We): JZZO 6 . __ l l

$. Design Electrical Rating (Net HWe): 114910_. ._ l l

6. Hamimum Dependable Capacity (Gross We): .116Z,0 l
7. Manimum Dependable Capacity (Net HWe) _URQ .,_,

j

- S. If Changes Occur in Capacity Ratings (! tem Numbers 3 through 7) $1nce Last Report, Give Reasons:

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9. Power. Level to Whict Restricted. If a.ny (Net HWe) _,.JMA
10. Reasons for Restr .tions, If Anyt 8

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_ ., l This Month Yr-to_Date Cumulative 11 Hours.In P',,orting Period 744 Bi lL0 91JL5 12, Number of Hours Reactor Was Critical 36LB. 6,0E.L 4h151  !

13. Reactor Reserve Shutdown Hours 0 _. 0___ 0_ l
14. Hours Generator 09-Line 27110.__ ),21.L <$ 0]Jd_ >
15. Unit Reserve $hutdown Hours _

0.,0 0 .

0. _. .,
16. Groas ihermal Cnergy Generated (WH) .. 613dd2J _22,.326,46620.. 14L11L134  !
17. Gross (1setrical Energy Generated (HWH) 196_,$40 . _J,$4_6,$JQ_ _..$Q,fgLf9L_,

18, Het Electrical Energy Generated (IMI) 1 & 200 7.267.850.__. _f8.,$61,234

19. Unit Service factor 37.(t 77.3_ _ 49, B_,,

20,' Unit Availability Factor. 37.0 77.3 49 A

21. Unit Capacity Factor (Using HOC Net) EB 73d. 4LA
22. Unit Capacity factor (Using DER Net) 21.3 72.3 4 5d ,,_.
23. Unit forced Outage Ante- _

, ' O .L_ 2.L 4L)._. .

24. $hutdowns scheduled Over Next 6 Honths (Type, Date, and Duration of Each):

Un1LLCysle_.Lt.efuellos.nutage_todeton..Detedst_20J.93L ALD91LISLFhta.NnlLL. .

__. wn_rrintntLin.ittrise. .

2$. If.$ hut Down.At End Of Report Period, Estimated Date of $tartupt N/A

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8igs..'1m 4 9de -gr0'ev+e-e*6 +yv>+ '+ysvag , r*'tf't- --'T-===--'We--w.,+- --em- T wt T g 'r w v v y,

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OPERAllHG DATA RfPORT 00cxti No.30-310 Daft Jaat_S J99L_

COHrttito ey 1.J.Jtollneen._

itttPHONC 1615La43-1520_

0118A11HL.51AIVS l Notes l

1. Unit Namet _$etWoJadLM01LIKo - l l
2. Reporting Period! JittehtL.1991 -

l l

3. Licensed Thermal Power (HWt): J4lbl_ _ l
4. Namepisto Rating (Gross h e): _122.0,(t .__, l
5. Design tiectrical Rating (Net HWelt J145.d_ . l l
6. Manimum Depeadable Capacity (Grocs HWe): JH2A - .

l l

7. Hanimum Dependable Capacity (Het HWe): J12110 1 _1
8. If thanges Occur in (apacity Ratings (! tem Numbers 3 through 7) Since last Report, Give Reasonst n._ _ . . - - ._ _,. .-
9. Power level to Which Restricted, If Any (Het HWe): ._J(/A -
10. Reasona for Restrictions, If Any: . tVA . - . _ -

This Month Yr-to.4 Jte Cumulative

11. Hours _in Hearting Period ___744 0.1h0 Wh02 _.
12. Number of Hours Reactor Was Critical L43 L 8.5.3bl _ 41G8
13. Reactor Reserve Shutdown Hours , 0_ 0 ,. -- Q._,_
14. Hourt Generator On-line ._ 114.0 B. ABZA. 4R10ALZ
15. Unit keserve Shutdown Hours .. _02D__ 0 ,,_

j IG. Gross-Thermal Energy Generated (HUH) ,.LA9LQ&L_ ._2a.652,06Lh _150 91L3.1.3

17. Gross Electrical Energy Generated (HWI! _ 05ad!1t._ -

9.673.075 _ SLJ50 ZR1

18. Net t1ec.trical tnergy Generated (HWH) _.__019Jt29 . .. L 31L B86 -.A6.9AL9D4
19. Unit service f actor 100A _ -, 74L 57.2 20, Unit Availability factor

_ JR0 cL _

$L Z_.,

21. Unit Capacity f actor (Using HDC Net) - 98 1 JMd . 5119.__
22. Unit Capacity f actor (Using OtR Net) 49 _ .92iL  % , %2
23. Unit forced OutaDe Rate- 0,D___ 3.L El,,_

24 $hutdowns'$cheduled Over Next 6 Honths (Type, Date, and Duration of tach)!

_UnLLLCycleJLt.efueling.sutageJLscheduled.lo btain_ttar.ch_1L_199L_andJLcurrmatlJ

_1thedultLaLalQ.Janoutsgt.

25. If Shut Down At End Of Report Period, tstimated Date of Startupt 3 /.A _
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[y UNIT SHUTDOWS APO FC40t REDUCTIONS Up.IT suME: Twe DATE: G1/CE/c2 REPORT MONTH: December 1991 COMPLETED BY:T 7. Mc11 omen TELEPMPiE:i6151 843-7528 Methcd of ticensea Cause and Cerrective Duration Shutting Down Event- Systce Conoonent Action ta I

Ne. I Date Type (Hours) Reason2 l Reactor 3

Report No. Code # Code 6 Frevent Recurrence ] ,

6 911207' -F" S 5 S 12/7/91, at 0434 EST. Unit 2 reactor power level was decreased h from 100 percent to 82 percent secause the No. 3 mi level control valves were indicating closed with erratic pusep readings on the No. 3 HDT pumps and 0 percent level on the Mc. 3 M T. Further power Tevel decrease free 82 percent to 58 percent was initiated at 0936 EST for replacement of one of

' the fevel control valves. On 12/8/91 at 1011 EST. reactor power level increase was initiated. i unit 2 was again operating at '

100 percent on 12/3/91, at 1421 EST and centinuad to operate at i 100 percent through the end of i Trecember . j l

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I:F Forced. 2 p,,,,,, 3 Methc4: h hibit GInstructions  !

5: Scheduled A-Equipment Failure (bplain) 1-Manual fer Preparation of Data  !

B-Maintenance or Test 2-Manual Scram Entry sheets for Iitensee ,

1: C-Refueling 3-Aetonatic Scrae Event Report (LER) Tile ,

D-Regulatory Restruction 4-Continuation cf histing Outage (NURE b1022) a, E-Operator Training and License G aeination S-Reduction  !

F-Administrative 9-Other-i 40perational Error (bytain) ' . h ibit I-Same Source 6 H-0ther {balain) -  ;

1