ML20070C806

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Monthly Operating Repts for Jan 1991 for Sequoyah Nuclear Plant Units 1 & 2
ML20070C806
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/31/1991
From: Hollomon T, Wallace E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9102260176
Download: ML20070C806 (10)
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Icnnoss e VMey AunWy PoM Oke hav NXX)Addy-Da sy Teniesee 37370 February 15, 1991 U.S. Nuclear Regulatory Commiesion ATTN Document Control Desk Washington, D.C. 20555 Gentlement In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - JANUARY 199'. MONTHLY OPERATING REPORT Enclosed is the Janaury 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) 843-8422.

Very truly yours.

TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licer. sing and Regulatory Ai'atrs Enclosure ec: See page 2.

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9102260176 9.10131 y jDR ADOCK 05000327 PDR ')d t

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2 U.S. Nuclear Regulatory Commission February 15, 1991 cc (Enclosure):

Mr. J. N. Donohew, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 INPO Records Center Institute of Nucicar Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. Ted Marston, Director Electric Power Research Institute P.O. Sox 10412 Palo Alto, California 94304 i

, NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy Tennessee 37379 Regional Administration j

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NK, 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 j e T

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6 TEhWESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOYAH NUCLEAR PIANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION JANUARY 1991 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 b

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l OPERAIl0NAL SE!ARY JNARY1991 UNIT 1 Unit 1 generated 871,480 megawatt hours (MW h ) (gross) electrical power  ;

during January, with a capacity factor of 100.8 percent. Unit 1 operated at  !

approximately 100 percent reactor power level the entire month.

UNIT 2 l 1

Unit 2 generated 791,150 MWh (gtoss) electrical power during January, with a capacity factor of 91.51 percent.

i on January 3, lo91, at 1321 Eastern standard time (EST), Unit 2 operators began a load reduction after they discovered problems with the No. 3 heater drain tank (ilDT) level control valves (LCVs). During the manual runback, an  !

automatic runback occurred when the No. 3 HPT bypass valves opened to divert flow to the main condenser. This automatic runback occurred without incident, and the unit stabilized at approximately 72 percent reactor power.  ;

In order to conduct repairs to the No. 3 !!DT LCVs, it was necessary to reduce reactor power to approximately 60 percent. Reducing power required getting the turbine electrohydraulic control (EllC) system back to normal and of f of "

the governor valve limiter, which had performed the automatic runback. During this reset process, the governor valves began closing and would not stop.

Investigation determined that the turbine EllC system was receiving an artificially high input for turbine impulse pressure caused by a dampening valve that had vibrated closed. Closure of the governor valves resulted in a turbine / generator trip on generator reverse pow :. A subsequent steam generator (S/G) high-high level resulted in an etigineered safety feature (ESF) actuation (feedwater isolation (FWI] and auxiliary feedwater [AFW) pumps startit.g). The reactor entered Mode 2.

Following investigation and corrective actions. Unit 2 was again tied online at 0415 EST on January 5,1991. Unit 2 reached 100 percent reactor power level at 2308 EST on January 7, 1991 and operated at near 100 percent through the end of January.

P0E0PERATED RELIEF VALVES (PORVs) AND SAFETY VALVES SMARY ii There were no challenges to PORVs or safety valves in January.

0FFSITE DOSE CALOUIATION MANE (0DCM) CEEES There were no changes to the ODCM during January. -

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, AVERACE DAILY UNIT POWER LEVEL j i

DOCKET NO. 50-327 UNIT No. , One DATE: _02-07-91 COMPLETED BY: T. J. Hollomon TELEPHONE: (615) 843-7528 MONTil: JANUARY 1991 1

AVERAGE DAILY POWER trVEL AVERAGE DAILY. POWER LEVEL DAY (MWe-Net) DAY , . .

(MWe-Net) 1 1133 17 1133 2 1131 18 11.34 _,

3 1129 19 1135 . , _ _

4 .1130 20 1139 5 _,

1131 21 1139 6 1132 _

22 1139 7 1132 23 1137 8 1131 24 1138 9 _

1133 2$ 1132 10 1132 26 1138 11 1133 27 1136 12 1132 28 1134-13 1133_ 29- 1135 14 1133 30 1136 15 1133 31 1135 16- 1132 >

AVERAGE DAI*,Y UNIT POWER LEVEL DOCKET NO. 50-329 UNIT No. Two DATE: __02-07-91 COMPLETED BY: T. J. Ho11omon TELEPHONE: (615) 843-7528 l MONTH: JANUARY 1991 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY

_ (MWe-Net) DAY (MWe-Not) 1 1126 17 1132 2 1127 18 1133

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3 677 19 _

1132 4 _ -33 20 1133 .

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_ 135 21 1133 6 657 22 1133 i

7 954 23 1133-l 8 1131 24 1132 i 9 1132 25 1132 10 1132 26 1132 11 1135 27

, 1132-12 1134 28 1133 13 1134 , 29 1132 14 1134 30 1133 15 __ 1134' 31 -- 1131-16 '1135

-OPERATING DATA REPORT

  • DOCKET NO. 50-327

.DATE _ reb. 7. 1991 COMPLETED BY f.1. Ho11 0 mi TELEPHONE f615) 843-7E2a__

OPERATING STATU$

-l Notes ll

1. Unit Namet'_ $th2Xah tinit One l. H.
2. Reporting Period .1anuary 1991

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3. Licensed Thermal Power (HWt): 3411.0 l 4, Nameplate Rating (Gross HWe):. 1220.6
5. Design Electrical Rating (Net HWe) _1148_0
6. Maximum Dependable Capacity (Gross HWe): _1162.0 l
7. Maximum Dependable Capacity (Net HWe):' 1122.0' 8.

JL' -l If Chan9es Occur in Capaci*y Ratings (Items Number 3 Through 7) $1nce tast' Report. Give Reasonst Jesuovah Nue1 A gr P1. ant salance of Plant tvitant anointern have attabl { thed, a more accurate _ arest ngglinum deoendable caneeliv f GMDC) and not maximum dgpandable canacity (HHDC) based on NRC

_ definitions.

9.

Power Level To Which Restricted. If Any (Net HWe)! N/A

10. Reasons For Restrictions. If Anyt N/A '.) '

This Month' Yr-to-Date- Cumulative

11. Hours in Reporting Period ,,,,,_ 744 144' 84.049
12. Number of Hours Reacter Was Critical 74(.0- 744.0 , 40.816
13. Reactor Reserve Shutdown Hoers'- ~0 0 'O
14. Hours Generator On-Line 744 0 744.0 39.840.0
15. Unit Reserve Shutdown Hours. 0. 0 - 0 .,,_ 0 i
16. Gross Thermal Energy Generated (HWH) i2.536.489.4 2.536.489.4 i 129.822.556
17. Gross. Electrical Energy Generated (HWH) ,,_B71.480 871.480 '43.992.066 18, Net Electrical Energy Generated (HWH) 840.681- _a 840.681 42.137.557
19. Unit Serviro Factor -100.0 100.0 g 47.4
20. Unit Availability Factor 100.0- 100.0 47.4
21. Unit Capacity Factor (Using HDC Net); 100.7 '100.7 ' '44.7
22. Unit Capacity Factor (Using DER Net) 100.7 100.7 44.7
23. Unit Forced Outage Rate ' _

M, 0.0 44.8

24. Shutdowns Scheduled Over Next 6 Honths (Type. Date ind Duration of Esch) l 25 -IF-$ hut Down' At End Of Report Period. Estimated Date.o': Startup ,,,,ti/1, i

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OPERATING DA7A REPORT

  • i DOCKET NO. 50-328 _.

.DATE Feb. 7. 1991 '

COMPttTED BY T. 3. Hollomon l

, TELEPHONE f6151 B43-752L,_

OPERAtlNG STATUS l Notes Li

1. Unit Name: tenuovth Unit two l ,
2. Reportlng Period: _ January 1991 ,-l j '
3. Licensed Thermal Power (HWt): J411.0 l l
4. Nameplete Rating (Gross HWe); ,,121(L6 _

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5. Design Electrical Rating (Net HWe): 1148.0 l l
6. Maximum Dependable Capacity (Gross HWe): 1162.0 l
L Maximum Dependable Capacity (Net HWe)!. 1122.0 l
8. If Changes Occur in Capacity Ratings (!tems Number 3 Through 7) $1nce Last Report..Give Reasons!-

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_ seauovah Nuclear Plant Balance _ of. Plant tytingngingars harg_.411ablished a

. more accurate _ GMDC and NMDC baigg[._on NRC definitight.-

9. Power Level To Which Restricted. If Any (Net HWe); N/A '

1 10. Reasons for Restrictions, if Any! N/A i

ThIs Month Yr-to-Date Cumulative-

11. Hours in Reportleg Period 744 7'44 76.009
12. Number of Hours Reactor Was Critical 744.0 '744.0 41.215
13. Reactor Reserve Shutdown Hours . O' 0- 0
14. Hours Generator On-Line 707.0 707.0- 40.267.4
15. Unit Reserve Shutdown Hourt _ - . 0.0 0- ~

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16. Gross Thermal Energy Generated (HWH) _2.316.660.3 '2.316.660.3 124.591.111
17. Gross Electrical Energy Generated ('WH) 791.1!io 791.150 =42.279.366
18. Net Electrical Energy Generated (HWi) 762.175 762.175 ' __40.388.253 i
19. Unit Service factor 95.0 95.0 s LO.,,,,,
20. Unit Availability Factor ._ 95.0 9s.0 53.0
21. Unit Capacity factor (Using HDC Net) 91.3 91.3. 47.4
22. Unit Capacity factor (Using DER Net) 91.3 91.3 47.4 l
23. Unit Forced Outage Rate- _. 5.0 B.0_ 40.0
24. Shutdowns Scheduled Over Next 6 Hsnths (7 f rpe .' ate, and-Duration of Each): .
25. If Shut Down At End Of Report Period, Estimated Date of Startup:; N/A' k

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  • DOCKET NO: 50-327 - ',

. UNIT SHOTDOWN5 AND POWER REDUCTIOt:5 UNIT NAME: _ _Jnt __._

l DA T E:__.2D _7ISL__ , ,

REPORT NONTH: Januarv 1991 COMPtETED BY:L_ L_tinihmon .

l- TELEPt10NE:I615) 843-7528 .*

Method of Licensee Cause and Corr

  • tive Duration 5 hatting,Down Event Systy Cyt Action to No. .Date Type l (Hours) Reason2 Reactor3 Report No. Code Code Prevent Recurrenca No activities during January 1991.

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I r I:F Forced 2 R2ason: h thod: kshibitGInstructions 5: Scheduled  : A-Equipment Failure (Explain) 'l-Maneal ' for Freparation of Data B-Maintenance or Test 2-Manual Scram ' Entry sheets for Licensee C-Refueling 3-Automatic Scram Ennt Report (LER} File D-Regulatory Restruction 4-Continuation of Existing Octatpe (MUREG-1022}

E-Operator Training and Eicense Examination 5. Reduction

F-Administrative .9-Other G-Operational Error (Explain) SEnhibit I-Same Sevrte H-Other (Explain)

_ - . - . - _ _ , _. _ _ _ _ ~ . - - - - - -- - -- -

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DCSEI C1: M-A'3

  • UNIT SPQJIIQiP45 AND PUwldt REDIKilONS (MIT NAMF:_ __ I w9 __

OAff:_QUQUJL_ .

REPORT month:jnary 1991 EOMrtETfD BV:TmJ,_lM h%n, IE t t PHOM :(fg !51 P U-%3 ,

Method of Licensee ~ Cause and Corre(tive l

Duration Shutting Down Event Systp E g ent A(tion to Frevent Reterrente No. Date Type I (Hours ) Reason 2 Reacto.3 Report No. Code Eode 1 950103 F 36.97 A 5 50-326/91001 IT LC On Janu ry 3.1931, at 132: (EST).

Unit 2 operators began a load reduction af ter they discovered problems with the No. 3 HDI LCVs.

During manual runback, an auto ip runback otturred i. hen the No. 3 mi r1 bypass valves epened to dieert flow to the main condenser. This auto

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runback occurred without incident.

E and the wait stabilized at 72 percent reacter power. In

'~ order to conduct repairs to the No. 3 HDT LCVs. it was necessary to reduce reactor power to 60 pertent.

Reducing power required getting the turbine EHC back to noririal and off of the governor valve (GV) limiter,i.hich had performed the auto runback. During this reset process, the GYs began closing and enould not stop, i.hicS resulted in a turbine and generator trip on 2

gwerator reverse power. A subsequent S/G Hi Hi level resulted in an ESF actuation (TWI and AFW pumps startieg). The reactor entered Mode 2. Investigatica determined that the turbina EHC system was receiving an artificially high input for turbine impvise pressure, caused by a dampening vaYve that had vibrated closed. Administrative (entrois have been initiated that prohibit the ese of the turbine centrol circuitry that utilized the turbine impulse input. Unit 2 was tied online at 0415 EST J,ca ry S. 1998, and reathed 100 percent reactor power level at 2303 EST en January 7 1991.

I F: Forced 2 Reason: 3Method: kshibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Freparation of Data B-ft+intenance or Test 2-Manual Scram Entry sheets for Licensse C-Refueling 34utomatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of E=isting Outage (NUREG-1922)

E-Operator Training and License Examination 5-Redection F-Administrative 9-Other G-Operational Error (Explain) 5 Exhibit I-Same Soorte H-Other (Explain)

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