ML20052G260

Monthly Operating Repts for Mar 1982

ML20052G260
Person / Time
Site:	Sequoyah
Issue date:	04/06/1982
From:	Dupree D, Eddomgs M, Mason C TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20052G254	List: ML20052G253 ML20052G260
References
NUDOCS 8205140460
Download: ML20052G260 (18)

Text

r

s. . wan 4 TENNESSEE VALIIY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT HONTHLY OPERATING REPORT MARCH 1, 1982 - MARCH 31, 1982 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328

LICENSE NUMBER DPR-79 ll l

Submitted By: g& __ )

Power Plant Superintendent i

t 8205140460 820409 gDRADOCK 05000327 PDR

TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 1-6 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . . 6 Licensee Events and Special Reports . . . . . . . . . . . . . . . . . . . 6-8 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . . . . . . 8 Operating Data Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9-11 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12-15 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 16 Field Services Maintenance Summary . . . . . . . . . . . . . . . . . . . . 16 i

, -+n ,.- , , . . -- ,- n- --

,w . , - - - - , - ---e + - a,--n-- - - - , , - -

Operationn Summary March, 1982 The following swnmary describes the significant operational activities for the month of March. In support of this summary, a chronological log of significant events is included in this report.

Unit 1 Unit I was critical for 510.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, produced 552,030 MWH (gross) with 4.14 percent station service use resulting in an average hourly gross load of 1,092,000 KW during the month. The net heat rate for the month was 10,670 BTU /KWH. There are 148.26 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 September 21, 1982. The capacity factor for the month was 63.8 percent. -

There were four reactor scrams, no manual shutdowns, and two power re-ductions during March.

Unit 2 Unit 2 was critical for 535.76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />, produced 301,940 MWH (gross) with 7.53 percent station service use, resulting in an average hourly gross load of 597,920 kW during the month. The net heat rate for the month was 11,570 BTU /KWH. There are 361.57 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target E00 exposure would be reached May 30, 1983. The capacity factor for the month was 34.3 percent.

There were six reactor scrams, one manual shutdown, and three power reductions during March.

_ gnificant Operational Events

^

Unit 1 Date Time Event 03/01/82 0001 Reactor in mode 5. Outage continuing for turbine vibration problems and replacement of reactor coolant pump

1. 2 motor.

03/08/82 1452 Reactor entered mode 4.

Sianificent Oparr,tienol Ev2nto (Continued)

Unit 1 Date Time Event 03/09/82 0200 Reactor entered mode 3.

1734 Reactor taken critical - mode 2.

03/10/82 0005 Reactor entered mode 1.

0142 Unit tied on-line.

0200 While placing a polisher in service the condensate flow was spiked which swang the MFP pressure causing feed-water oscillation. The turbine tripped on high steam generator level

1. 4, the reactor tripped on Lo-Lo steam generator level #2.

0436 Reactor-taken critical - mode 2.

0526 Reactor entered mode 1.

0629 Unit tied on line.

2028 Polishers isolated when a control power fuse blew in the condensate demineralizer plant. MFPT's tripped due to low seal water injection pres-sure, therefore, the turbine tripped.

The reactor tripped due to Lo-Lo steam generator level #3.

03/11/82 0043 Reactor taken. critical - mode 2.

0230 Reactor entered mode 1.

I 0325 Unit tied on line.

0346 Reactor tripped on a Lo-Lo steam generator level #2 due to feedwater

!- flow / steam flow mismatch during power ascension.

0650 Reactor taken critical -' mode 2.

l 0750 Reactor entered mode 1.

0943 Unit tied on line.

s. Significent Operetlonni Evznts (Continued)

Unit 1 Date Time Event 03/11/82 1023 Reactor tripped on Lo-Lo steam generator level #1 due to feedwater

-flow / steam flow mismatch during power ascension.

1210 Reactor taken critical - mode 2.

1305 Reactor entered mode 1.

1347 Unit tied on line.

03/12/82 2200 Reactor power 100%, producing 1130 MWe.

03/31/82 2359 Reactor in mode 1 at 100% power producing 1140 MWe.

Unit 2 03/01/82 0001 Reactor was in mode 3. Investigating control bank D rod M-4 indicator problem.

2130 Reactor entered mode 4.

03/02/82 0413 Reactor entered mode 5.

2057 Reactor entered mode 4.

03/03/82 04004 Reactor entered mode 3.

2200 Reactor critical - mode 2.

2245 Reactor entered mode 1.

2357 Unit tied on line.

03/07/82 0951 While investigating ground problems on the MFPT's, both MFPT's tripped, 2A AFWP was started and load re-duction initiated. The reactor tripped on steam flow /feedwater flow mismatea.

1827 Reactor taken critical - mode 2.

Significent Operational Eventa 4

(Continued)

Unit 2 Date Time Event 03/07/82 2000 Reactor entered mode 1.

2058 Unit tied on line.

03/10/82 2028 Polishers isolated when a control y power fuse blew in the condensate demineralizer plant. MFPT's tripped due to low seal water injection pres-

) sure, therefore, the turbine tripped.

'The reactor tripped due to Lo-Lo steam generator levels.

03/11/82 0325 Reactor taken critical - mode 2.

1145 Unit tied on line.

I 2258 Turbine tripped due to an oil leak in the EHC system. Reactor power reduced to 9% and holding.

03/12/82 (111 Unit tied on line.

03/15/82 1410 Reactor in mode 1 at 75% power, pro-ducing 860 MWe.

1 03/18/82 0720 Performed 10% load drop test from 75% to 65% reactor power.

1000 Performed the 50% load drop test.

1005 Reactor in mode 1 at 25% power,

producing 213 MWe. Began reducing

! power to take.the reactor to mode 3.

1029 Unit off line. Reactor in mode 2.

l i 2350 Reactor entered mode 3.

, 03/17/82 0001 Reactor entered mode 4.

1700 Reactor entered mode 5. Repairs to be made to 2-FCV-3-280A. ,

j 03/20/82 1737 Reactor entered mode 4.

i 03/21/82 0019 Reactor entered mode 3.

i

Significant Optrational Evente 1 '

(Continued)

Unit 2 i

Date Time Event 03/22/82 0900 Reactor taken critical - mode 2.

1054 Reactor entered mode 1.

1210 Unit tied on line. [

1358 A blown fuse in the condensate demineralizer plant isolated the polishers, both MFPT's tripped on low seal water injection pressure.

The reactor tripped on Lo-Lo steam generator level #2.

1757 Reactor taken critical - mode 2.

2032 Unit tied on line.

2042 The MFW valve failed to open, reactor tripped on Lo-Lo steam generator level #4.

2203 Reactor critical - mode 2.

2354 Reactor entered mode 1.

03/23/82 004'9 Unit tied on line.

03/25/82 2355 Reactor in mode 1 at 100% power, producing 1138 MWe. Initial 100%

reactor power.

03/27/82 2110 Performed the 10% load injection test.

2200 Started the 50% load injection test.

2203 MFPT's tripped due to low seal water injection pressure thus the reactor tripped. ,

03/23/82 1808 Reactor taken critical - mode 2.

2118 Unit tied on line.

Significant Operetionsl Evento (Continued)

Unit 2 Date ,7fime Event 03/28/82 2127 Reactor tripped on Lo-Lo st'am e

generator level #4 due to feed flow / steam flow mismatch during start-up.

03/29/82 0212 Reactor taken critical - mode 2.

0443 Unit tied on line.

03/31/82 2359 Reactor in mode 1 at E 75% increasing to.100%.

PORV's and Safety Valves Summary No PORV's or safety valves were challenged during-the month.

Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during March 1982, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuc1 car Regulatory Commission.

LER SUBJECT SQRO-50-327/82-018 Containment lower compartment average air temperature was 124.19'F due to train A cooler temperature control valve set incor-rectly.

SQRO-50-327/82-024 Turbine building sump and condensate demineralizer radiation monitors 2-RM-90-212 and -225 inoperable due to crud buildup on flow switches.

SQRO-50-327/82-025 Pressurizer level channel 1-LT-68-335 inoperable due to limiting safety system setpoint has con-servative than Tech Spec caused by instrument drift.

SQRO-50-327/82-027 Preparing for SI-566 ERCW Flow Verification Test, containment spray heat exchanger IA discovered with low ERCW flow due to 15 gallons of clams.

1

' Licensee Events end Special Reports (Continued)

LER SUBJECT SQRO-50-327/82-028 Number 4 cold leg accumulator inoperable due to low boron concentration caused by leak through in flow control valve. ,

1 SQRO-50-327/82-029 Glycol containment isolation valve 1-FCV-61-194 ,

would not reopen after stroke test due to t conductor GIB1 that controls solenoid not terminated.

SQRO-50-327/82-033 Containment process radiatiou monitors 1-RM-90-106 and -112 inoperable due to closed isolation valves caused by work without proper authorization.

SQRO-50-327/82-034 During SI-566 ERCW flow verification test con-tainment spray heat exchanger IB outlet flow balancing valve 1-HCV-67-537B found closed and tagged under a released hold order.

SQR0-50-327/82-035 During SI-566 ERCW flow verification test, the auxiliary control air compressor found tripped on high temperature due to stuck solenoid valve.

SQRO-50-328/82-019 Turbine driven AFW pump inoperable due to out-board seal packing blowing out caused by normal wear and deterioration.

SQR0-50-328/82-020 EGTS room cooler B inoperable due to blown fuses caused by short in solenoid coil of 2-FSV-67-338.

SQR0-50-328/82-021 Shutdown rods in bank A in excess of + or

- 12 steps of rod position indicators caused by misinterpretation of tech specs.

SQRO-50-328/82-022 During SI-159.2 lower containment airlock was found inoperable due to braces over tightened during SI-159.1 giving a bad seal.

SQRO-50-328/82-023 Loop 4 main steam header remote shutdown pressure channel 2-PT-1-26C inoperable due to amplifier card failing caused by heat from steam leak.

SQRO-50-328/82-026 Containment sump level indicator 2-LT-65-176 inoperable due to bellow leakage.

SQR0-50-328/82-030 AFW automatic control valve level controller 2-LIC-3-173 inoperable due to failing low caused by loose connection.

Licensee Evento end Special Reports (Continued)

LER SUBJECT f

SQRO-50-328/82-031 RWST level transmitter 2-LT-63-50 inoperable due to low readings caused by dirty potentiometer from normal dust accumulation.

SQRO-50-328/82-032 Rod position indicator on control bank D inoperable due to indication of 0 caused by a defective con-nector.

{ Special Reports

! There were no special reports sent during the month of March.

i Offsite Dose Calculation Manual Changes

There were no changes to the Sequoyah Nuclear Plant ODCM during the month of March.

4 i

I i

( .

l 3

,  ?

t

" O -

OPERATING DATA REPORT DOCKET NO. 50-327 DATE March 5, 1982 COMPLETED BY M. Eddings TELEPHONE 615/751-0343 OPERATING STATUS

1. Unit Name: Sequoyah one Notes

2. Reporting Period: March 1982

3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross MWe): 1220.58

5. Design Electrical Rating (Net MWe): 1128

6. Maximum Dependable Capacity (Gross MWe): 1163

7. Maximum Dependable Capacity (Net MWe): 1128

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 744 2,160 6,577

12. Number of Hours Reactor Was Critical 510.9 892.6 3,693.9

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 505.5 850.4 3,540.8

15. Unit Keserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,648,397 2,504,134 10,569,088

17. Gross Electrical Energy Generated (MWH) 552,030 846,190 3.492,140

18. Net Electrical Energy Generated (MWH) 529,137 795,885 3,322.910

19. Unit Service Factor 67.9 39.3 53.8 l 20. Unit Availability Factor 67.9 39.3 53.8

21. Unit Capacity Factor (Using MDC Net) 63.1 32.7 44.8 t 22. UnitCapacityFactor(UsingDERNet) 63.1 32.7 44.8 l 23. Unit Forced Outage Rate 32.1 49.4 29.1

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

REFUELING / MODIFICATION OUTAGE--SEPTEMBER 21 (scheduled) 6 months.

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 7-1-81 l

(9/77) 6 UNIT SHUTDOWNS AND POFER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah One DATE COMPLETED BY M. Eddings REPORT MONTH March 1982 TELEPHONE 615/751-0343 1

c^ N o eo 3 Licensee $ Cause & Corrective No. Date ". S$ 8 ojg Event @% E*e Action to p $$ $ .@ tj j Report # $i i Prevent Recurrence 85

" e *t .a*g &" "

o" o

o Turbine #11 bearing excessive vibration 2 820209 F 217.7 A 4

1. 2 reactor coolant pump replacement due to

~

electrical problems.

8 820310 F' 4.5 A 3 I, -1 steam generator level #2 S/C due to 1 ,

swings in levels during startup.

?

9 820310 F 7.0 Blown fuse at condensate system caused loss A 3 of suction to main feed pumps resulting in Rx trip.

10 820311 F 5.9 A 3 Reactor trip on 10-10 level steam generator

1. 2 due to swings in levels during startup.

11 820311 F 3.4 A 3 L -1 S/G level #1 steam generator hard to control swings in levels during startup.

I 2 3 4 F: Forced Reason: Method:

S: Scheduled A-Equipment Failure (Explain) Exhibit G-Instructions 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-D-Regulatory Restriction 4- Cont . of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction.

G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (fx,, lain) '

Exhibit I-Same Source

~ ~

1 AVERAGE DAILY UNIT POWER LEVEL z

DOCKET NO. 50-327 UNIT one DATE March 2, 1982 COMPLETED BY M. Eddings TELEPHONE 615/751-0343 MONTH MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 1107 2~ 0 18 1100 3 0 19 1106 4 0 20 1106 5 0 21 1109 6 o 22 1104 7 0 23 1112

• 8 0 24 1100 9 0 25 1106 10 157 26 1108 11 153 27 1106 12 947 28 1102 13 1101 29 1076 14 1101 30 1102 15 1101 _

31 1104 16 1102 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.

(9/77)

OPERATING DATA REPORT DOCKET NO. 50-328-DATE April'6, 1982 COMPLETED BY David Dupree TELEPHONE 615/751-0343 OPERATING STATUS

1. Unit'Name: Sequoyah Two Notes

2. Reporting Period: March 1982

-3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross MWe): 1220.5

5. Design' Electrical Rating (Net MWe): 1148

6. Maximum Dependable Capacity (Gross MWe): .1183

7. Maximum Dependable Capacity (Net MWe): 1148

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 744 2,160 3,674

12. Number of Hours Reactor Was Critical 535.8 1,287.7 1,544.9

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator.On-Line 505 1,166.4 1,180

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (NWH) 942,115.5 1,741.353.3 1,757,267.3

17. Gross Electrical Energy Generated (MWH) 301,940 537,400 539,304

18. Net Electrical Energy Generated (MWH) 279.190 475.470 475.420

19. Unit Service Factor 67.9 54.0 32.6

20. Unit Availability Factor 67.9 54.0 32.6

21. Unit Capacity Factor (Using MDC Net) 32.7 19.2 11.4

22. UnitCapacityFactor(UsingDERNet) 32.7 19.2 11.4

23. Unit Forced Outage Rate 32.1 46.0 67.4

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

ICE WEICHING PER TECH SPECS--May 5, 1982

'25. If Shut Down At End Of Report Period, Estimated Date of Startup: March 10. 1982

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

Forecast Achieved INITIAL CRITICALITY 11-5-81 11-5-81 INITIAL ELECTRICITY 12 31-81 12-31-81 COMMERCIAL OPERATION 6-1-82 N/A (9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS ' DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE April 6. 1982 COMPLETED BY David Dupree REPORT MONTH MARCH 1982 TELEPHONE 615/751-0343 page 1 of 2 i

1 em n o ee 3 Licensee $ Cause & Corrective No. Date ". OO E oS$ Event @% $*o Action to p  %$ E .E i$ $ Report # $'8 Prevent Recurrence

$5 $ USc o zmg m" o" u

o 8 82-3-1 F 71.9 A 4 Unit tripped while attempting to perform SU-9.3 (50% load reduction).

9 82-3-7 F 'll*1 A 3

"# * #'E' * **

flow / feed flow mismatch causing Rx trip.

.L Y 10 82-3-10 F 15.3 A 3 m use at n . DI cause lw seal inser-tion pressure causing a turbine trip, Rx trip.

11 82-3-11 F 2.2 A 5 L w EHC fluid pressure caused a turbine trip only Rx dropped to 92 power.

1 82-3-18 S .3 B 5 50% load rejection test (startup test 9.3).

12 82-3-18 S 97.6 B 1 Repair leaking feedwater valve on #1 S/C.

13 82-3-22 F 6.5 A 3 Blown fuse at Cond. DI, power supply cabinet EN$$Nek!ih k5 EESpI * ' *

• E*

1 2 3 4 F: Forced 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-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction.

G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source 1

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE April 5. 1982 COMPLETED BY David Dupree REPORT MONTH MARCH 1982 TELEPHONE 615/751-0343 l

page 2 of 2 1

~

em n o ee 3 Licensee $ Cause & Corrective No. Date e SE @ .o S y Event $$ E^o Action to p %5 E ,@ tj j Report # M] '8 Prevent Recurrence 85 a =m &*

• o a

21l o u

14 82-3-22 F 4.1 A 3 Rx trip caused by MFW isolation valve failed to open when level dropped in #4 S/G.

15 82-3-27 F 23.2 A 3 Loss of hotwell level causing low suction

, causing turbine to trip, Rx trip.

.L 16 82-3-28 F 7.2 G 3 Hi-hi S/G level cause turbine trip i Lo-lo S/G level cause.Rx trip.

1 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G-Instructions 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. Eveut Report (L2R) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction.

G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source 1

~

q

..o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Two DATE April 1982 COMPLETED BY David Dupree TELEPHONE 615/751-0343 MONTH MARCH 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 832 2 0 18 355 3 0 19 0 4 285 20 0 5 363 21 0 6 429 22 14 7 204 23 396

'8 309 24 874 9 347 25 1008 10 409 26 1108 11 107 27 1018 12 271 28 0 13 410 29 200 14 596 30 300 15 726 31 700 16 811 i

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.

1 (9/77)

I i

Plant Maintent.nce Summary The following significant. maintenance items were completed during the month of March 1982:

Mechanical Maintenance No maintenance reported on CSSC equipment this month.

Electrical Maintenance

1. Repairs were completed on Unit I and 2 reactor coolant pump motor.

Ir Instrument Maintenance None reportable.

+ Field Services Maintenance Work continues on the following items:

] 1. A reactor head venting system is being installed on both units. The base plates for the power cabinets have been fabricated and they wil1~

be installed within the next few weeks. -

2. Conduit is being installed to facilitate high range area radiation monitors for the residual heat removal lines and containment spray heat exchanger room 1A.

' 3. Conduit work is complete and cable pulling is approximately 50% complete to provide lights and telephones to the personnel airlocks on both units.

4. Exposed cables in areas outside primary containment containing one oc both safety related divisions are being coated with Flamastic.

5. The flow switches on radiation monitor 1-RE-90-170 are being replaced.

6. A post-accident sample system for Unit 1 is being installed to obtain designated liquid and gas samples during and after a postulated event.

The following work was completed during the month, i 1. Yard security lighting located behind the diesel generator building is

complete.

i 1

E

.----- - - .