ML20066C718

Monthly Operating Repts for Nov 1981.Narrative Summary Encl

ML20066C718
Person / Time
Site:	Sequoyah
Issue date:	12/02/1981
From:	Dupree D, Eddings M TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20066C717	List: ML20066C715 ML20066C718
References
NUDOCS 8211100294
Download: ML20066C718 (16)

Text

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TENNEShEEVALLEYAUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT NOVEMBER 1, 1981 - NOVEMBER 30, 1981 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79

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Submitted By:

Power Plant Superintendent i

e, 8211100294 811215 PDR ADOCK 05000327 R PDR

TABLE OF CONTENTS 1

Operations Susunary . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Significant Operational Events . .................. . . . 1-5 PORV's and Safety Valves Susunary . . . . . . . . . . . . . . . . . . . . . . 5 Licensee Events and Special Reports .................... 5-6 Offsite Dose Calculation Manual Changes ................. 6 Operating Data Unit 1 ............................... 7-9 t

Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-12 Plant Maintenance Sununary . . . . . . . . . . . . . . . . . . . . . . . 13 Outage Maintenance Sununary . . . . . . . . . . . . . . . . . . . . . . . 14 4

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Operatiens Summary November 1981 The following rummary describec the significant operational activities for the month of November. In support of this summary, a chronological log of significant events is included in this report.

Unit 1 Unit I was critical for 654.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, produced 629,210 MWH (gross) with 4.5 percent station use, resulting in an average hourly gross load of 600,635 KW during the month. The net heat rate for the month was 10,849 BTU /KWH.

There are 202.2 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached July 25, 1982. The capacity factor for the month was 73.9 percent.

There were four reactor scrams, no manual shutdowns, and four power reductions during November.

Unit 2 Unit 2 was critical for 213 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for low power testing. There are 383.0 full power days estimated remaining until the end of cycle 1 fuel.

There were two reactor trips, one manual shutdown and no power reductions.

Significant Operational Events Unit 1 Date Time Event l 11/01/81 0001 Reactor in mode 1, 80% reactor power, 828 MWe.

l t 0041 Performed SI-78 and adjusted ethe reactor power range to 75%.from 80%.

2310 Holding 90% reactor power to perform SI-137.2.

11/02/81 0400 Reactor at 100% power,1110 MWe.

t l 11/C6/81 1325 Reactor tripped on Lo/Lo steam generator level. MFPT tripped due to loss of suction when the con-densate demineralizer bypass valve failed to open in's timely manner, k

Signifierst Oparetienel Evsnts (Continued)

Unit Date Time Event __

11/07/81 0957 Reactor taken critical.

1035 Reactor in mode 1.

1047 Rolled turbine.

. 1107 Turbine tripped.

1109 Reactor tripped on a Lo/Lo steam generator level due to a steam flow /feedwater flow mismatch during power ascension.

1304 Reactor taken critical.

1515 Reactor in mode 1.

1551 Rolled turbine.

1631 Tied generator on line.

11/09/81 0027 Stopped power ascension at 78%

reactor power, 840 MWe, to repair a leak on the #3 heater drain e tank pump 1A.

11/10/81 1245 Reactor at 100% power, 1110 MWe.

11/21/81 0320 Reduced reactor power to 96%, 1115 MWe due to oscillations in #3 heater drain tank pump flow.

l 0940 Turbine dropped to 91% power to com-pensate for the #3 heater drain tank bypassing to the condenser./

1007 Reduced reactor power to 74% to com-pensate for the #3 heater drain tank bypass.

1107 Load decreased to 50% for maintenance on #3 heater drain tank.

2340 Reactor power held at 80% for con-densate demineralizer regeneration.

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11/22/81 0230 Reactor power holding at 95% waiting condensate demineralizer regeneration.

, Significent Operctien91 Evrnts (Continued)

Unit 1 Date Time Event 11/22/81 0600 Reactor power at 97%.

0710 Reactor power reduced to 94% for the main generator slot temperature problems.

1800 Reactor power at 99%.

11/23/81 0953 Reactor tripped on Lo/Lo steam generator level. Caused by closure of loop 4 MSIV during the performance of a surveillance instruction.

11/24/81 0040 Reactor taken critical and holding at 2% power due to main condenser air inleakage problems.

11/25/81 0024 Generator tied on line.

2200 Holding at 30% reactor power for improvement in secondary chemistry.

11/26/81 1136 Commenced power ascension.

1241 Reactor tripped on Lo/Lo steam generator level at 49.5% power when A MFPT tripped while starting B MFPT.

B MFPT was not properly reset, causing a low MFPT condenser pressure and trip of A MFPT.

2140 Reactor taken critical.

2317 Generator tied on line.

1425 Reactor at 100% power. /

11/28/81 11/29/81 2032 Reactor power reduced to 97%, 1094 MWe due to vibration on the turbine #11 bearing.

11/30/81 0825 Water box B-1 taken out of service.

Load dropped 50 MWe to 1044 MWe.

1741 Water box B-1 returned to service.

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! 2359 Reactor power at 97%, 1094 MWe.

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- Significent Operatiensl Evrnts s-(Continued)

Unit 2 Date Time Event 11/01/81 0001 Reactor in mode 4 at 340*F, 800 psi.

11/02/81 1813 Reactor entered mode 3.

11/04/81 0720 Safety injection' occurred when a logic card shorted out in the SSPS. E 1100 gpm pumped into RCS from RWST.

11/05/81 2140 Reactor entered mode 2.

2225 Reactor taken critical.

11/09/81 0732 Reactor tripped for SU-7.7.

1620 Reactor taken critical.

11/10/81 0957 Reactor tripped for SU-7.7.

1450 Reactor taken criticai. g 11/11/81 0800 Reactor power E 3% for SU-8.5.3.

i 1335 Reactor power to 0%.

I j 11/12/81 1830 Reactor power 3%.

i 11/13/81 1949 Turbine tripped due to exciter problems.

11/14/81 1341 Reactor in mode 1 at 5% power.

1732 Reactor power decreased to 3% for W-10.5.

2033 Began reactor shutdown to mode 4 to investigate and repair exciter '

problems.

2037 Control band B rod F-2 stopped driving in AOI-2E inplemented.

11/15/81 0040 All control rods fully inserted.

0629 Reactor entered mode 3.

0828 Reactor tripped.

1 0930 Reactor entered mode 4.

o Sianificnst Operr.tional Events (Continued)

Unit 2 Date Time Event 11/16/81 1000 Reactor entered mode 5.

11/19/81 0020 Reactor entered mode 4.

11/30/81 2359 Reactor in mode 4 at 205*F 8 340 psi. Exciter off site for repairs.

PORV's and Safety Valves Summary -

No PORV's or safety valves were challenged during the month.

I Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during November 1981, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

SQRO-50-327/123 Centrifugal charging pump 1B-B tagged out for test and not released prior to mode 4 entry.

SQRO-50-327/125 Pipe chase on Al wall at elevation 685 not seismically qualified. Causes ABGTS inoperable.

4 SQRO-50-327/127 Pressurizer level and pressure transmitters 1-LT-68-320, and -335 and 1-PT-68-323 setpoints found less conservative.

SQRO-50-327/128 Pressurizer power operated relief valve 1-PCV-68-340A leaking to pressurizer relief tank due to improperly adjusted valve stem.

SQRO-50-327/129 Power range channel N-41 of the neutron instru-mentation declared inoperable due to failed oscillator. /

SQRO-50-327/130 AFW Pump 1B-B failed to start following con-i trolled disagreement signal.

Auxiliary building vent rad monitor inoperable

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SQRO-5'0-327/137 due to defective motor.

SQRO-50-327/139 Control rod indication system inoperable due to out of calibration.

SQRO-50-328/122 RWST boron concentration below' limits and a portion of heat traced piping below 145'F.

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.,' - Licensen Events rnd Sp2cini Rrpsrts (Continued)

SQRO-50-328/124 Unit 2 entered mode 4 without analyzing D/G fuel for insolubles.

t SQRO-50-328/126 'NIS power range channel III (N-43) inoperable due to power fuse being inadvertantly pulled.

SQRO-50-328/131 Centrifugal charging pumps out of service for maintenance on bypass isolation valve 2-63-564.

SQRO-50-328/133 Power operated relief block valve 2-FCV-68-333 inoperable due to broken limit switch.

SQRO-50-328/135 Containment sump level transmitter 2-LT-63-179 inoperable due to high readings.

SQRO-50-328/138 High thrust bearing temperature on reactor conlant pump #3.

Special Reports i

There was one special report sent during the month of November.

81-7 Safety injection occurred due to SSPS logic boardy short circuit - Tech Spec 3.5.3

-Offsite Dose Calculation Manual Changes There were no changes to the Offsite Dose Calculation Manual during the month of November 1981.

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OPERATING DATA REPORT DOCKET NO. 50-327 DATE December 2. 1981 COMPLETED'BY Mike Eddings TELEPHONE 615-842-0295 OPERATING STATUS

1. Unit Name: Sequoyah 1 Notes

2. Reporting Period: November 1981

3. Licensed Thermal Power (MWt): 3411 .

4. Nameplate Rating (Gross MWe): 1220.58

5. Design Electrical Rating (Net NWW): 1128

6. Maximum Dependable Capacity (Gross MWe): 1163

7. Maximum Dependable Capacity (Net MWe): iigg

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period - 720 3697 3697 12 *. Number of Hours Reactor Was Critical 654.4 2,109.2 2,109.2

13. -Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 643.8 2,031.1 2,031.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,900,801 6,985,833 6,985,833

17. Gross Electrical Energy Generated (MWH) 629,210 2,009,660 2,009,660

18. Net Electrical Energy Generated (HWH) 600,635 1,908,412 1,908,412 l

19. Unit Service Factor 89.4 55.4 55.4

20. Unit Availability Factor 89.4 55.4 55.4

21. Unit Capacity Factor (Using MDC Net) 73.9 46.2 46.2

22. Unit. Capacity Factor (Using DER Net) 73.9 46.2 /46.2

, 23. Unit Forced Outage Rate 10.6 44.6 / 44.6 l 24. Shutdowns Scheduled Over Next 6 Nonths (Type, Date, and Duration of Each): .

Tech. Spec. Ice Weighing February '82 27 Days j 25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 '

INITIAL ELECTRICITY - 8-21-80 7-22-80 COMMERCIAL OPERATION 7-1-81 'g 7-1-81 b" (9/77) j ,-., e **

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT Seouoyah 1 DATE December 1. 1981 COMPLETED BY . M. Eddines TELEPHONE 615-842-0295 HONTH November DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 818 17 1074 2 1062 18 1097 3 1075 19 1092 4 1073 20 1050 t 5 1071

• 21 837 6 590 22 1070 7 49 23 424 8 278 24 0 9 840 25 217 10 1057 26 151 11 1073 27 322 12 1074 28 1079 13 1074 29 1099 14 1079 30 1064 /

15 1080 31 N/A 16 1075 INSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in I the reporting month. Compute to the nearest whole megawatt.

(9/77)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327

~ UNIT NAME uniinv h i -

.i DATE Dec =her'1. 1981 COMPLETED BY -

Mik, vaatng.

REPORT MONTH wny..w,, TELEPHONE 615-842-0295 S

em n o ao 3 Licensee $ Cause & Corrective No. Date ~

e dE E oS$ Event fui E*e Action to i

g  %$ E .8 d j Report #  %'8 8,'8 Prevent Recurrence l

85 a

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J 3 81/11/06 F 27.1 B 3 Con D.I. was bypassed due to electrical short.

Unit could not recover in tine.C.B.P.'s &

M.F.P.T.'s tripped. ,

4 81/11/23 F 38.5 A 3 Lo-Lo level #4 S/G.

r T 5 81/11/26- F 10.6 A 3 Low M.F.P.T. Cond. Vacuum.

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's 1 2 3 4 fi F: For6ed Reason: Method:

• Exhibit G-Instructions .

( S: Scheduled A-Equipment Failure (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 (NUREG-

,f D-Regulatory Restriction 4- Cont . of Existing 0161) t E-Operator Training & License Examination Outage f F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 .

(9/77) H-Other (Explain) Exhibit I-Same Source it

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OPERATING DATA REPORT DOCKET NO. 50-328 e DATE December 2. 1981 COMPLETED BY David Duoree TELEPHONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Sequoyah Two Notes

2. Reporting Period: wnvoms,r. 1981

3. Licensed Thermal Power (MWt): 1411

4. Nameplate Rating (Gross MWe): 1220.5 -

5. Design Electrical Rating (Net MWe): 1148

6. Maximum Dependable Capacity (Gross MWe): 1185

7. Maximum Dependable Capacity (Net MWe): iian

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

i This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 720 720

12. Number of Hours Reactor Was Critical 213.5 213.5 213.5

13. -Reactor Reserve Shutdown Hours 0 0 __

0

14. Hours Generator On-Line 0 0 0

15. Unit Reserve Shutdown Hours .0 0 0

16. Gross Thermal Energy Generated (MWH) 3200.9 3200.9 3200.9

17. Gross Electrical Energy Generated (MWH) 0 0 0

18. Net Electrical Energy Generated (MWH) 0 0 0

19. Unit Service Factor 0 0 0

20. Unit Availability Factor 0 0 0

21. Unit Capacity Factor (Using MDC Net) 0 0 0

22. Unit Capacity Factor (Using DER Net) 0 0 ' 0

23. Unit Forced Outage Rate 0 0 < 0

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

- Ice Weighing (5-5-82). Requirement Per Technical Specifications

25. If Shut Down, At End Of Report Period, Estimated Date of Startup: 12-27-81

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 11-5-81 s 11-5-81 INITIAL ELECTRICITY 12-31-81 NA COMMERCIAL OPERATION 3.&-1-82 \ NA i *

(9/77)

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Seauoyah Two DATE necamher 2. 1981 COMPLETED BY , David Dupree TELEPHONE (615) 842-0295 MONTH Novenber 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 t 5 0 21 0-6 0 22 0 7 0 23 0 8 0 24 0 9 0 0 25 10 0 26 0 11 0 27 0 12 0 28 0 13 e 29 0 14 0 30 _

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15 0 31 NA 16 0 e

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. '

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(9/77)

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f UNIT SifUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 _

UNIT NAME un,,nv h ri.m *

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DATE Decembe'r 2. 1981' COMPLETED BY David Dupree REPORT MONTH November TELEPHONE (61si R42-n20s S

em u '$ w 3 Licensee $ Cause & Corrective No. Date "o 00 E' oj$ Event @$ E*e Action to y@ E ,E d j Report # $3 8. 3 Prevent Recurrence

$5 E $E m'

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Emfo u 81/10/01 S 720 A 1 Initial Criticality Testing and Mainteaance (Maintenance on the Exciter) 9 1

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j 1 2 3 4 d F: Forfed Reason: Method: '

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual

((j -B-Maintenance or Test C-Refueling s .

'2-Manual Scram.

3-Automatic Scram.

for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-y D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage

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F-Administrative G-Operational Error (Explain) 5-Reduction 9-Other 5 -

1 (9/77) H-Other (Explain) Exhibit I-Same Source

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, f. Plant Maint:nince Summarv The following significant maintenance items were completed during the month of November 1981:

Mechanical Maintenance

1. Repaired the 1A2 diesel generator starting air compressors.

2. Replaced the mechanical seals on all four boric acid transfer pumps.

3. Repaired a steam leak on 2B main feed pump turbine.

4. Repaired a leaking weld joint on a 1" line between the positive displacement pump relief valve 62-518 and a 4" Jine to the volume control tank.

5. Began work on the Unit 2 steam dump modifications.

6. Repaired pressure centrol valves 1-PCV-3-122 and 2-PCV-3-122.

7. Repairs started on the Unit 2 main exciter.

Electrical Maintenance

1. Installed new bearings in the 2A-A auxiliary feedwater pump mot 9r.

2. Initiated repairs on the Unit 2 generator exciter.

3. Repaired Unit 2 hydrogen igniters.

Instrument Maintenance None reportable.

Field Services Maintenance Unit 1

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1. A reactor vessel head venting system is being installed per THI Lissons Learned LL-2.1.13.

2. Prefabrication of the new pressurizer instrumentation condensate pots has be, gun.

3. Work continues on the installation of a post accident sampling system which will add the capability of obtaining designated liquid and gas samples during and after postulated event.

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,1, Field S2rviczs M intenenca e

(Continued)

Unit 1

4. Modiciations to suction damper 30-4A and the power supply for purge air supply fan B is complete.

5. The installation of an air flow rate limiting device in line with the discharge of fire pump 1B air release valve is complete.

Unit 2

1. A reactor-coolant sampling system to determine crud levels has been installed.

2. The carbon steel ERCW supply and lines to the incore instru.sent room chiller 2B is being replaced with stainless steel.

Unit 0 or Items Affecting Both Units

1. Cables in junction boxes that contain the control switches for interim ABSCE dampers that were blocked open are being removed.

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2. Environmentally qualified solenoids are being installed on various dampers.

3. Hanger modifications are continuing.

4. The replacement of the 4-inch piping to HVAC equipment serving the electric board rooms and main control room continues with the fabrica-tion and installation of hangers and piping on the train B return line.

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5. Door A-183 is being replaced to achieve positive access accountability.

6. Coating all exposed cables with Flamastic in areas outside primary containment containing one or both safety related divisions continues.

7. A 3' x 3' opening in the A1 line wall in the auxiliary building .is being closed with a 3-hour rated fire barrier. /

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