ML20091K960

Monthly Operating Repts for Apr 1984

ML20091K960
Person / Time
Site:	Sequoyah
Issue date:	04/30/1984
From:	Dupree D, Eddings M, Mason C TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8406070260
Download: ML20091K960 (30)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION APRIL 1, 1984 - APRIL 30, 1984 j ..

UNIT I DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted By: ,,

Fower' Plant Superintendent

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TABLE OF CONTENTS

. Operations Summary . . . . . . . . . . . . . . . . . . . . . . .1 Significant Operational Events . . . . . . . . . . . . . . . . . 1-2 i:

4 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . .2 Reports Licensee Events . . . . . . . . . . . . . . . . . . . . . . 3-4 4 Diesel. Generator Failure Reports . . . . . . . . . . . . . 4 Special Reports . . . . . . . . . . . . . . . . . . . . . .4 Offsite Dc;e Calculation Manual Changes . . . . .. . . . . . .4 Operating Data Unit'1 . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7

i. Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . 8-10 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . 11-27 i

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3 Oparatiens Summary April, 1984 The following summary. describes-the significant operational activities for the. month of April. In support of _this summary, a chronological log of significant events is included in this report.

Unit'l

' Unit 1 was critical for 86.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, produced 11,540 MWH (gross), resulting in an average hourly. gross load of.297,193 kW during the month. There are 369.45 full power days estimated remaining until the end of cycle 3 fuel.

With aL capacity factor of 85 percent, the target EOC exposure would be reached July 10, 1985. The capacity factor for the month was 1.4 percent.

There were 1 reactor scrams, no manual shutdowns, and no power reductions.

Unit 2 Unit 2 was critical for 719.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 855,590_ MWH (gross),

resulting in an average hourly gross load of 1,182,419 kW during the month. There are 108.37 full power days' estimated remaining until the end of1 cycle 2 fuel._ With a capacity factor of 85 percent, the target EOC exposure would be reached September 5,1984. . The capacity factor for the month was 99.2. percent.

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

'Significant Operational Events Unit 1 Date Time Event 04/01/84 0001 The reactor was in mode 5. The refueling / modification outage continuing.

04/10/84 1454 The reactor entered mode 4.

04/12/84 0905 The reactor entered mode 3.

04/15/84 1817 The reactor was taken critical.

04/17/84 0254 The reactor entered mode 1.

0515 The turbine tripped due to generator relay problems (the unit was not on-line).

0600 The reactor entered mode 2.

1158 The reactor entered mode 1 and was holding at 6% reactor power.

Sigaificant Operational Events Unit 1 (Continued)

Date Time Event 04/17/84 1546 The unit was tied on-line.

2117 The turbine tripped when the stator cooling water pump burned up.

2148 The reactor tripped due to a Lo-Lo

1. 3 steam generator level. (Mode 3)

, 04/18/84 1012 The reactor was taken critical.

1118 The reactor entered mode 1. '

1214 The unit was tied on-line.

-1700 The reactor was in mode 1 at 30% ,

power, producing 316 MWe, '

04/19/84' 2100 A thimble plug in the seal table started leaking.

2117 Began reducing load.

2133 The reactor tripped on a Lo-Lo #1 steam generator level.

04/20/84 0655 The reactor entered mode 4.

0932 The reactor entered mode 5.

04/30/84 2359 The reactor was in mode 5. The forced outage due to the thimble plug leak continues.

Unit 2-Date Time Event 04/01/84 0001 The reactor was in mode 1 at 100% power, 04/30/84- 2359 prodacing 1183 MWe.

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

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Licensee Events and tpecial Reports T .:

The'following Licensee Event Reports'(LER's) were sent during April 1984,

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to the Nuclear Regulatory Commission.

LER. DATE TIME UNIT MODE DESCRIPTION'0F EVENT SQRO-50-327/1-84019 03/07/84 '

1 5 Analysis of the ice condenser basket weights obtained during surveillance testing in accordance with T.S.3.6.5.1 indicated that the group 3 - row I average basket weight was below the design limit

_ of 1080 pounds with a 95% level of confidance.

SQRO-50-327/1-84020 03/09/84 0339 1 6- A high radiation alarm was 03/26/84 0854 1 6 actuated which caused a containment

' ventilation isolation (CVI) to 4

occur. Investigation revealed 5

that a voltage spike occurred as a result of EMI generated by switch actuation of the low flow alarm and by the opening of the motor-

operated disconnects (MOD) in the ts,' switch yard due to a breaker

.Y i . failure.

s SQRO-50-327/1-84021 03/22/84 0255, 1 6 A high radiation alarm was

~ 03/30/84' 0219 I 5 actuated which caused an ABI to w .-

t 03/31/84 0215 'I' 5 occur. Investigation revealed t 04/01/84 0624)' 1 - 5 that the spent fuel pit radiation 04/03/84 0731 1 5 monitor had alarmed due to the movement of contaminated C-zone clothing and trash by the monitor.

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SQRO-50-327/1-84022 03/30/84 0730 1 5 A high radiation alarm was

( 04/09/84 0740 1 5 actuated which caused a CVI to occur. Investigation revealed that a voltage spike occurred as a result of EMI and another incident i, was caused by a personnel error l- during a modification of the CVI circuit. ,

[- SQRO-50-328/2-84004 03/26/84 3854 1 6 The loss of a 5.9kV unit board

! 2 1 causing undervoltage on a 6.9kV 04/02/84 1026 1 5 shutdown board, resulting in I

2 1' the standby diesel generators 04/03/84 0836 1. . 5 starting. Investigation L -2 1 revealed that unit board 1A and IC lost power due to a C-phase to ground fault on a 500kV breaker

, which cleared the 500kV switchyard l' bus section 2.

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Licensee Events and Special Reports (Continued)

@ DATE TIME UNIT MODE DESCRIPTION OF EVENT SQRO-50-328/2-84005 03/29/84 1015 2 1 SI-269, " Channel Function Test of ESF Instrumentation for Automatic Switchover to Containment Sump,"

was not completed within the 1.25 surveillance interval allowed by the T.S.

SQRO-50-328/2-84006 04/06/84 0110 2 1 A high radiation alarm was 04/08/84 0439 2 1 actuated which caused a CVI to occur. Investigation revealed that a voltage spike occurred as a result of EMI which was spurious in one incident and caused by personnel error in the other incident.

Diesel Generator Failure Reports There were no diesel generat.or failure reports transmitted during the month.

Special Reports There were no special reports transmitted during the month.

Offsite Dose Calculation Manual Changes There were not any changes to the Sequoyah Nuclear Plant ODCM during the month.

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- OPERATINGcDATA REPORT-39". E p

, :n DOCKET'NO. 50-327 g' g. ' .

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DATE MAY 10 1984 COMPLETED'BY M. G..EDDINGS E TELEPHONE (615) 870-6248 w . .

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- LOPERATING STATUS'

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31 h 0 NIT NAME:fSEQUOYAHINUCLEAR PLANT,-UNIT ~ l' NOTES:

[2k REPORTiPERIOD : APRIL 1984_ '

d32LICENSEDtTHERMAL: POWER (MWT):. 3411.O

54. NAMEPLATE'RATINGL(GROSS MWE):' 1 2 2 0'. 6 2 75.fDESIGK ELECTRICAL-RATING (NET {MWE): 1148.O'

-6.fMAXIMUM: DEPENDABLE CAPACITY,(GROSS MWE): - 1183.O

.7p MAXIMUM' DEPENDABLE. CAPACITY-(NET MWE):

1140.O-

/C.'IFiCHANGES OCCUR'_.IN' CAPACITY' RATINGS (ITEMSiNUMBERS 23LLTHROUGH 7)SINCELLAST' REPORT,-GIVE REASONS:-___---- - _

Y .: --p -- ------- -------- -_

=--------- ----.

4> p-.----------------_- ------ - -

(9.. POWER LEVEL.TO WHICH RESTRICTED,IFTANY(NET MWE):------ -

!10.1 REASONS FOR. RESTRICTIONS,IF ANY:--- = ---- -- _--

. - - ------ ------.--- ------------: _ _ _ - - - - - - - = - - -_ _ .

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THIS MONTH- ~YR.-TO-DATE CUMULATIVE c11E HOURSiIN REPORTING PERIOD 719.00 2903.00 24840.00 I12h NUMBER IOF1 HOURS REACTOR WAS CRITICAL. 86.90 1101.80 >15543.36-L13 7 REACTOR: RESERVE, SHUTDOWN HOURS 0.00 O.00 O.00-14.: HOURS GENERATOR ON-LINE 38.80 1000.10 15113.25-15.cUNIT' RESERVE SHUTDOWN' HOURS' .

O.00 O.00 0.00

'16.nGROSS1 THERMAL ENERGY-GENERATED (MWH) '44926.96 L2915234.67 48407084.97 L17M GROSS. ELECTRICAL ENERGY GEN. (MWH) 11540.00 967690.00 - 16346826.00

'1DO NETPELECTRICALiENERGY GENERATED (MWH) .7084.00 922151.00 15699079.00' I19.l UNIT SERVICE' FACTOR- _

5.40 :34.45 60.84

/20.? UNIT" AVAILABILITY; FACTOR 5.40 34.45 60.84-t21.juNIT CAPACITY' FACTOR (USING MDC NET) O.86 27.67 55.05

!22.EUNIT CAPACITY FACTOR (USING DER NET)- 0.86 27.67 ~55.05

'23. UNITJFORCED OUTAGE RATE 87.84 35.17 .19.37 24..SNUTDOWNSiSCHEDULED OVER NEXT:6 MONTHS'(TYPE, DATE. AND DURATION OF EACH):

-- -- - . _ _ - -- ---- ---- -=----.- -------- --

25. IFjSHUTDOWN:AT-END-OF REPORTLPERIOD, ESTIMATED DATE OF STARTUP:

} .May,_L2,_19_S4__ _ ___ _=_

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" NOTE THAT THE THESYR.-TO-DATE AND CUMULATIVE. VALUES 1HAVE-BEEN UPDATED.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT one DATE May 10, 1984 COMPLETED BY Mike G. Eddings TELEPlf0NE (615)870-6248 MONTH APRIL DAY. AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,

1. N/A 17 . 0177' 2

!^ 18 0236 3 N/A 19 0287 4 N/A 20 N/A

-5 'N/A 21 7 N/I.;

6 N/A 22 N/A' ?

7 v/A 23 N/A' 8 N/A' 24 N/A 9 N/A 25 N/A 10 N/A 26 N/A

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11 N/A 27 N/A' 12 N/A 28 N/A 13 N/ 29 N/A 14 N/A

'30 N/A 15 N/A 31 .

16 N/A ,

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)

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UNIT SHUTDOWNS AND' POWER REDUCTIONS ~ DOCKET NO. 50-327

' UNIT..NAME Sequoyah one

. DATE May 10, 1984 COMPLETED BY- .M. G. Eddings REPORT MONTH APRIL TELEPHONE -(615)870-6248 q -

% o gg % c y tj Licensee -y Cause & Corrective No. Date E O8 2 y Ij 2 Event 5% 8% Action to p ge 2 5y* Report ! g? g] Prevent Recurrence.

5" ?d5 N* 5" e

5 840220 S 399.8 C 4 .

Refueling Outage Core #2 6 840417 F 15.0 A 3 Stator Cooling Water Pump Failure 1

y 7 840419 F 265.4 A 3 Thimble Guide Tube Leak at Seal Table 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

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OPERATING DATA REPORT DOCKET NO. 50-328 DATE MAY 10,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6248 OPERATING STATUS

' 1, UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:

2. REPORT PERIOD: APRIL 1-30,1984 3, LICENSED THERMAL POWER (MWT): 3411.0

4. NAMEPLATE RATING (GROSS MWE): 1220.6

5. DESIGN' ELECTRICAL RATING (NET MWE): 1148.0 6c MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 7s MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0

<a IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 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 719.00 2903.00 16800.00

-12... NUMBER OF HOURS REACTOR WAS CRITICAL 719.00 2842.80 13203.87

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

.14. HOURS GENERATOR ON-LINE 719.00 2838.60 12992.92

-15.-UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS' THERMAL ENERGY GENERATED (MkH) 2449814.48 9598159.93 42016227.74

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 844050.00 3321520.00 14353460.00

~18. NET ELECTRICAL ENERGY GENERATED (MWH) 811190.00 3203403.00 13821140.60

.19. UNIT SERVICE FACTOR 100.00 97.78 77.34 20, UNIT AVAILABILITY FACTOR 100.00 97.78 77.34

21. UNIT CAPACITY FACTOR (USING MDC NET) 98.28 96.12 71.66 J22. UNIT CAPACITY FACTOR (USING DER NET) 98.28- 96.12 71.66

23. UNIT FORCED OUTAGE RATE O.00 2.22 7.81 L24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

. .szat_embst._L_j.2 8_4_Refyeli,,ng/MiJisat i_of_________ .,_____ ____ _ _ __________ _____

'25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

. NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-328 UNIT .Two DATE May 10, 1984 COMPLETED BY D. C. Dupree TELEPHONE (615)870-6248 MONTH APRIL DAY ~ AVERAGE DAILY _ POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ,

(Mwe. Net) ,

1 1138 17 - 1134' 2 1136 Ig 1135

~3 1136 19 1134 4- '1136 20 1133 5 1135 - 21 113$;

6 1136 22 1133 )?

7 1136 23 1133 8 1133. 24 1133 9 1137 25 1134 10 -1138- 26 1136

.11 1135 27 1136' 12 1136 28 1136 13 11'37 29 1135 14 1136 ~30 1133 15 1136 31 .

i- 16 1135 INSTRUCTIONS On this format,.'. list the average daily unit power level in MWe-Net for each day in

.the reporting month. Compete to the nearest wnole megawatt.

(9/77)

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UNIT SHUTDOWNS AND POWER' REDUCTIONS DOCKET NO. S0-328

. UNIT NAME Sequovah Two DATE' Mav~10; 1984 COMPLETED Bli D. c. nuoree -

REPORT MONTH APRIL' ' TELEPHONE. (615)870-6248 u

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, - gg  % c y tj Licensee p. Cause & Corrective No. Date g,. Oy 8 'g O g Event $$ 8% Action to-p Se 2 6y* Report ! g] 8? . Prevent: Recurrence

-SP $55g &" .@"

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'NONE I 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-C.ont. 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 "

Plant Maintenance Summary The following significant maintenance items were completed during the month of April 1984:

Mechanical Maintenance

1. Welded scab plates on the ERCW piping downstream of valves 67-551A and 67-146.

2. Seal welded a hinge pin on 1-VLV-5-820 "A" MDAFWP discharge check valve.

3. Disassembled the RTD manifold flow element 1-FE-68-7 for orifice plate inspection. No problems were found.

4. Replaced the steam traps on the TDAFWP turbine.

5. Set the stroke on 1-PCV-68-340B.

6. Assisted in the recovery and replacement of the D-R incore thimble.

7. Per EN DES direction disconnected the hangers from loops 3 & 4 FW lines.

8. Replaced the 1-FCV-62-70 operator diaphragm.

9. Balanced RCP's 1-3 and 1-4.

Electrical Maintenance Unit 1

1. Unit 1 incore flux mapping system was found to have insufficient paths for a complete flux map. The detector drives were suspected of having loose clutches; this was checked out and found to be in error. The problem was determined to be blocked thimble tubes which would not allow the detectors to be driven fully into the reactor core. In the process of cleaning the thimble tubes a failure of the seal resulted in ejecting the thimble tube into the incore instrument room. The thimble tube was very hot radiologically and exposed the incore instrument room to a high radiation field. In addition, the seal table leak introduced abnormally high temperatures and steam into the incore instrument room.

The hot thimble was removed, the incore instrument room decontaminated and the electrical equipment was inspected for possible problems. The thimble tubes were cleaned by an outside vendor. The class 1E equipment environmental qualifications were reviewed for possible detriments to qualified life and the equipment was deemed suitable for service. The incore drives were inspected and the drive motor overload relays and detector cables were replaced, and the drive units were returned to service after the inspection and repairs.

2. The unit 1 main generator tripped on generator differential. Investigation determined that the actual problem was a trip # rom the volts per hertz relays.

The possible cause was an excessively fast rate of voitage buildup as the operator ramped the voltage up following exciter field breaker closure.

Additional exciter control problems were attributed to the misalignmen* of the exciter field breaker. The generator exciter breaker was correctly racked in and the generator was returned to service.

l P_1a,nt 1 Mointene.nce Summary .

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-(Continued) l Electrical Maintenance.

(Continued)

Unit 1 (Continued)

3. .USit I feedwater isolation valve 1-FCV-3-47 motor. failed due to the geared

-limits being disengaged for maintenance,and a sticking auxiliary contact on the open contactor. The motor and auxiliary contact were replaced, the limits were set, and the valve was returned to service.

, 4. Unit 1 CRDM's and RPI's were reconnected for unit.1 startup. Several RPI problems were encountered due to bad connector pins and mositure introduced into the connectors during decontamination of the reactor cavity. CRDM and RPI systems were successfully returned to service.

5. Unit 1 1C 6.9kV unit board tripped during ungrounding procedures. The most probable'cause is accidental actuation of the alternate feeder breaker cell switch while removing the grounding barrier. The board was returned to service with no problems.

6 Adjusted' and/or replaced as required the limit switches on:

. 1-FCV-1-7, 1-LCV-62-118A, 1-FCV-3-156A, 1-PCV-65-87, 1-FCV-62-77, 1-FCV-1-4, and 1-FCV-3-47.

, 7. Removed the unit 1 #3 heater drain tank pump motors. The motors were rewound

[ to higher temperature insulation grade and reinstalled.

8. The IB main transformer low voltage bushing circulation oil pump motor tripped due to a bad breaker.- The breaker was replaced and the pump was returned to service.

9. Performed routine maintenance of the unit I reactor trip breakers during the r_ refueling outage.

10. Repaired an oil leak on the unit 1 #3 RCP MTR oil lift system.

11. Repaired 10 unit 1 ice condenser air handling units.

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Unit 2

1. Adjusted and/or replaced as required the limit switches on: 2-FCV-1-25, 2-FCV-62-48, and 2-FCV-30-14.

2. Repaired the auxiliary switch on *he unit 2 reactor trip breaker.

3. Replaced a shorted coil on 2-FSV-67 1338 which caused the EGTS A train to be out of service.

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Ple-t M*.intenrnco Summary (Continued)

Electrical Maintenance (Continued)

-Unit 0 (Common)

1. IB-B diesel generator was inoperable due to shorted winding in the soak-back pump motor control transformer. The transformer was replaced. The DG was

. returned to service with no problems. The remaining control transformers will be inspected.

2. Replaced tl.e low Jacket water indicating light on IB-B DG.

3. 2B-B diesel generator-(DG) accidently started while troubleshooting the 2B-B diesel generator room exhaust fans. The DG was returned to standby condition.

t 4. Replaced the compressor motor on I glycol chiller.

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. Plant Maintinsncm Summary ~

Electrical Maintenanca LIST M. REPORT BY C+ID' LPTR 12:54:49 05-04-84 PACE 1, .

DATE. C0rP0 TENT. . . . . FAILURE DESCRIPTION...... CAUSE-0F FAILURE......... CORRECTIVE ACTION........ P R 011. . . .

04-01 2-MTR8-3 >207 EGT RM COOLER FAN MOTCR SHORTED COIL ON REPLACED COIL ON FLOW SDL NONE.

UGULD NOT START FSV-67-338 SLOUING FUSES (W_VE

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l IN BREAXER CONTROL _

CIRCUIT 04-05 1-MTRB-52-18 /2 LUBE OIL PUMP 1 CONTROL CONTROL TRANSFCRMER HAD REPLACED TRANSFORMER AfD ~ 1-84-133

-P TRANSFORMER WOULD NOT BURNED LP ~BLOUN FUSES CPERATE 03-23 2-FCV-1-25 VA.VE LIGHTS WERE SHOWING LIMIT SUITCH WAS REPLACED LIMIT SUITCH N0tE INCORRECT VALVE POSITION DEFECTIVE 02-22 1-FCV-1-7-B VALVE LIMIT LIGHTS UERE LIMIT SUIICH UAS REPLACED LIMIT SUITCH NONE' NOT SHOUING ACTUAL VALVE DEFECTIVE CUE TO HEAT POSITICH

, 04-04 2-EB-82-28 -8 GOVERNGR ON ENGINE 1 DIL UAS FOUMD IN PLUG, CLEANED PLUG AND ADJUSTED 2-84-59 UCULD HDT CPERATE ACTUAL CAUSE IS UhKNDUM GOVERNOR LEVER 03-28 0-MTRB-311-154 OIL PUMP MOTOR RUNd <0R UATER DID NOT HAVE PROPER ADJUSTED COOLING UATER NONE o A-A ABOUT 9 MINUTES THEN DISCHARCE PRESSURE CONTROL VALVE TRIPS 02-03 24EV-1 8 FLOU CONTRDL VALVE LIGHTS LIMIT SUI 1CH ARM WAS TIGHTENED LIMIT SUITCH NONE WERE NOT SHGUING ACTUAL LOOSE ON SHAFT PREVENTING ARM VALVE POSITION LIMIT SUITCH FROM MAXING UP 03-13 1-LCV-62-18A-A HOLDUP TAM LIMIT ACTUATCR ARM HAD TL'RNE0 ADJUSTED LIMIT SUITCH NONE SWITCHES UERE NOT SHOWING ON VALVE SHAFT DUE TO ACTUATOR ARM ACTUAL VALVE POSITION NORMAL WEAR 03-21 1 -ENS- 8? B DIESEL GENERATOR 1B-B POSSIHLY, GOVERNCR MAY LINED UP DIESEL AND NONE WOLLD HOT STABELIZE AT NOT HAVE BEEN RUN BACK RESTARTED 400 RPM ALL THE W 03-24 14E-3-173A- B RAMP CONTROL SUITCH FOR SUITCH HAD BoCKEN DURING REPLACED BROKEN RAMP HONE SGM2V LEVEL CONTROL VALVE OPER ATION FOR UNKN0'.H SUITCH UAS BROKEN REASON 03-22 14rrR A-74 A RHR PUnP 1A-A MOTOR WOULD DIRTY CONTACTS CAUSING CLEANED AND RESET 1-84-132 NOT START ARCHING AND MICALIGNMENT CCNTACTS ON PUMP RUN

P1 nt Maintenance Summary  ;

Eltetrical Maintenanca LIST M.REPCRT BY OID LPTR 12:54:49 05-04-84 PAGE 2 DATE. C0rP0 TEN T. . . . . FAILLHE DESCRIPTION....... CAUSE C;- FAILL9E. . . . . . . . . CCRRECTIVE ACTION......... PROM....

RELAY 04-15 1-TR-61-138 TEMPERATURE RECORDER UAS RIGH RESISTANCE OF CABLE' .RECRIMPED WIRE I-84-137 PRINTING CFF SCALE 1R/3.22 AT ELECTRICAL CONNECTIONS AT PEN 22 PENETRATION 22 03-20 2-EERC-99-KH/3 BREfXER 52H CONTACT ANGLE IkOS HOLDItG 52H PENT THIN ANGLE IRON BFCK 'NONE 19-G S0.? TIMES FAILS TO MAKE SUITCH LWS TOO THIN TO CORRECT POSITION. UE UP PREVENTING BKR FROM CAUSING ANGLE IRON TO ARE PURSUING A THICKER TRIPPING FROM MAIN BEND OUT OF POSITICN ANGLE IRON CONTROL RM HANOSUITCHES 01-24 1-ZS 156A AU) FU VALVE POSITION LIMIT SUITCH UAS LOOSE ADJUSTED LIMIT SUITCHES NONE LIGHTS UERE NOT SHOUING - DUE TO tORMAL LT.AR ACTUAL VALUE POSITION PREVENTItG LIMITS FROM MAKItiG LP -

04-06 1-PSV-65-81 HAND SUITCH UGULD NOT CRYDon RELAY MAD INTERNAL REPLACED CRYDON RELAY NONE OPERATE DEFECT 2.

YO4-06 1 -PCV-65-87 PRESSL9E CONTRCL VALVE LIMIT SUITCH UAS REPLACED ADJUSTED LIMITS- NONE STAYS OPEN RECARDLESS OF PREVICUSLY WITHOUT BEING ULV POSITION FUNCTIGmLLY TESTED OR

. ADJUSTED 03-21 1-TN8-52-19 -B D/CEN 10-8 INDICATING 18-8 UATER TEMP LIGHT REPLACED LIGHT SCC (ET Of NONE LICHT UCULD NOT COME ON SOCKET LAD STOPPE9 LOW JACKET UATER TEMP UORKItG DUE TO AGE AND ANNUNTIATOR NORMAL LEAR 04-09 1 -ZS 4-T VALVE LIMIT LIGHTS UERE LIMITS LOJLO NOT MO W DUE REDLACED LIMIT SUITCH NONE NOT SHOUING ACTUAL VALVE TO MATERIAL DEFECT OF POSITION LIf1IT EUITCH 04-06 1-F5V-3-47-8 LIMIT SUITCt!ES UERE OUT A'ORMAL UEAR OF SUITCHES, REPLACED DEFECTIVE TORaE NONE OF ADJUSTMENT TORGL'E SUITCH HAD BROKEN SUITCH AND ADJUSTED LIMIT SUITCHES 04-01 1-IGN-268-517 U-1 ICE CONDENSOR PROB A8LY EROKE WHILE REPLACED HYDROGEN IGNIIOR NONE HYDROGEN IGNITOR UA3 MAINTEWiCE UCRK UAS BROKEN BEING PGFORMEO AROtJND IGNITGR

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7 Plent Miinten*nce Summary

_(Continued)

Instrument Maintenance 1.: During the month there were three (3) auxiliary building isolations.

Two were initiated because of high background levels of the spent fuel pit and the other was because of airborne activity. There were tu spurious actuations. Earlier inLthe month, the auxiliary building vent rad monitor was modified to replace air flow AP switches with a model having reset deadband and to install an EMI filter on AC power cables to the monitor.

2. During the month there.were three (3) Unit I containment vent isolations (CVI) and 2 Unit 2 CVIs. Two of the Unit I and one of the Unit 2 CVIs

.were contributed to EMI.

3. Containment sump level transmitter 1 LT-63-179 drif ted high during the period the incore thimble guidetube was leaking. The transmitter was topped off and returned to service. This is only the second transmitter on the unit I which has been topped off since they have been filled with silicon oil. .The transmitters on unit 2 have been topped off a total of 13 times.

~4. Instruments in the incore instrument room were inspected and recalibrated following the leak caused by the failure of the incore thimble tube.

' Five qualified transmitters and six other transmitters were subjected to the transient and all were found to have drifted high. The qualified transmitters were from +.35% to +2.37% high. The non qualified.trans-mitters were from +.75% to 5.27% high.

5. Tested and verified operation of unit 1 and unit 2 PORV auxiliary control room channels after a wiring error was discovered and corrected. Details are available in LER-084-023.

6. During monthly testing of UHI level switches, found 1 switch on unit 1 out of technical specifications tolerance. All other switches on unit 1 and all unit 2 switches were within tolerance. All switches had been within tolerance for the preceeding five months.

7. Began a qu'arterly surveillance program for units I and 2 to check calibration of the reactor coolant system RTD bypass manifold flow switches. This is a result of the switches being found out of calibration numerous times during calibration at ' refueling outages, from other calibrations done by MRs, and NRC IE Information Notice No. 83-65.

Unit 1

1. Recalibrated set points and TACF'd pressurizer tailpipe temperature j instrument channels to clear alarms which were in due to elevated temperature caused by safety valve problems. Setpoints will be re-evaluated during the current startup.

J r +- . - -, . - - - , , - .-m,.m.v- , - -, -,+-,,--e- +-----,-+e---- -%c---,w -,>,.-rw-e-yw,w emryme y .-r---ve- e. ,p r .. +ew+ . m-w ee y 4- - ,--e r -

Plant Maintenance Summary (Continued)

Instrument Maintenance (Continued)

Unit 1 (Continued)

2. Piping associated with the rcot valve and condensate pot for pressurizer level channel 1 LT-68-320 were straightened to reduce the difference in indicated level with the other channels.

3. Replaced the pressure switches for the suction supply to the motor driven auxiliary feedwater pumps with qualified switches for 0588.

4. Recorded data during heatup needed by Westinghouse to complete the scaling on the reactor vessel level measurement system. They are currently scheduled to be on site May 14 for 10 days to calibrate the system to the final values.

Unit 2

1. RPI channel L-3 showed signs of a high resistance connection inside containment. High voltage was applied to the field cable following IMI-85 to correct the problem.

2. Performed response time test of both reactor trip breakers as a result of maintenance which is now scheduled to be done on the brea'ters every six months.

A i

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u ii

INSTRUMENT MAINTENANCE

SUMMARY

FOR THE MONTH OF APRIL 1984' Page 1 of 6-EFFECT ON SAFE NATURE OF ' OPERATION OF CAUSE OF RESULTS OF ACTION.TAKEN TO DATE -SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION ~ MALFUNCTION PRECLUDE RECURRENCE 04/05 85 Z-XX-85 Rod position None Bad cable None Repaired' cable connection erratic. connection. A-239271.

04/08 1 1-PCV-1-5 PORV won't open None- Bad None Replaced positioner & Cal' with loop 1 pcsitioner. I/P. 'A-239301 controls.

04/09 63 1-LI-63-60 Lvl ind. reads None Xatr out of None Recal Xmtr. -A-086991 higher than enl.

others.

t 04/24 30 2-TS-30-156 Htrs won't come None Hole in sense None Replaced sense line & recal on. line. TS. A-247375.

04/18 03 1-FY-3-35A Pegged low. None Air in sense None Bled xatr & recal.

line. A-247197.

04/19 03 1-LM-3-156A Replace I/P. None I/P housing None Replaced I/P & recal, cracked. A-282083.

06/17 68 1-TI-68-309 Check Temp Loop None None, None Verified Cal. A-285322.

Cal Verifying.

04/20 61 1-TR-61-138 Check recorder None Leak at seal None Verified recorder.

erratic. readings. table. A-238085.

INSTRUMENT MAINTENANCE

SUMMARY

FOR THE MONTH UF APRIL 1984 Page 2 of 6 EFFECT ON SAFE NATURE OF OPERATION OF CAUSE OF RESULTS OF ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE R2CURRENCE 04/18 68 1-FIS-68-7 Check alm switch. None Out of cal. None Recal FIS. A-239755.

04/14 90 1-RR-90-106A Recorder & None Bad cable & None Repair & recal recorder.

indicator differ. amp bd. A-247190.

04/18 68 1-FIS-68-49 Check alm switch. None Out of cal. None Recal FIS. A-239756 04/09 03 1-LCV-3-175 Replace relay. None Heat None Replaced relay.

A-247657.

8 04/09 03 1-LCV-3-174 Replace relay. None Heat None Replaced relay.

A-247658.

05/03 01 1-PCV-1-5 Vlv opens in None V1v gasket None Replace gasket.

auto. leaks. A-238091.

05/03 01 1-PCV-1-12 Vlv pos. leaks None Air leak None Replace gasket.

air. A-245631.

04/23 01 2-FT-1-3A Hi stm flow alm. None. Out of cal. None. Cal FM-1-3A & FS-1-3A.

A-242316.

04/23 68 2-LT-68-367 Funct. test of None Unacceptable None Replace & cal ind.

2-LT-68-370 ind. ind. A-285251.

W

. . INSTRUMENT-MAINTENANCE SUf9tARY- ,

FOR THE MONTH OF APRIL 1984. ,

Page 3 of 6 EFFECT ON SAFE .

NATURE.0F OPERATION OF .CAUSE OF . RESULTS OF- ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE' 04/09 68 1-TE-68-324 Cable broken. None ONSMMM broke None Replaced RTD. A'-234724.

cable.

03/31 90 0-RM-90-225 Lo'flo als won't' None Flo switch. None Cleaned flow switch, come in. A-241589.

04/19 63 2-LI-63-179 Lvl ind, reads None" Xmte out of None Recal x:str. A-244890.

high. cal, h04/18 77 2-LT-77-410 Lvl ind. None Xmtr out of - None. Recal xatr. A-117950.

e, reads Hi. cal.

i 04/10 03 1-LCV-3-174 Air supply builds None No problem None No problem found.

, too slow. -found. A-239461.

I t ,

j 04/10 03 1-LI-3-38 LI reads zero. None Isol vlv plug None~ Pressure opened viv.

stuck. A-239370.

4 l 04/10 63 1-LI-63-109 Reads higher than None No problem None No problem found. A-239388. i l other channels. found.

4 1

4 l 04/09 63 1-LI-63-99 Xmtr failed-Hi. None Xmtr out of None Recal xatr. A-120423.

! cal.

4 1

l

INSTRUMENT MAINTENANCE

SUMMARY

FOR THE MONTH OF APRIL 1984 Page 4 of 6 EFFECT ON SAFE-NATURE OF OPERATION OF CAUSE OF RESULTS OF ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION- PRECLUDE RECURRENCE-04/09 63 1-LT-63-129 Not ind same as None Instr out of None Recal xatr. A-092572.

others. cal.

04/11 43 1-H2AN-43-210 Flo status lite None Shorted / None Corrected' ground. A-244129.

is on with grounded wire.

analizer in standby.

04/14 68 1-LI-68-320 7% diff between None Lost filled None Back filled sense line, channels. leg. A-285316.

04/16 68 1-LR-68-339 Reads Hi. None 1-TC-68-2 out None. Recal, 1-TC-68-2.

of Cal. A-247472.

04/18 68 2-TS-68-316 Perform loop None R/I out of None Recal R/I. A-239289 check, cal.

04/03 85 1-ZS-85 Replace rod None Bad bistable. None Replaced & recaled histable Lottom bistable. A-244109.

04/10 68 1-PIC-68-340B Spray cont. not None V1v stem out None Aligned stem & stroked vlv.

responding of alignment. A-243074.

correctly.

04/11 68 1-TI-68-316

• Ind pegged hi. None TM out of None Recal TM. A-239467 cal.

L

.A.

INSTRUMENT MAINTENANCE

SUMMARY

FOR THE MONTH OF APRIL 1984 Page 5 of 6 EFFECT ON SAFE NATURE OF OPERATION OF' CAUSE OF RESULTS OF ~ ACTION.TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE-04/06 30 2-FE-30-242 ' Low flo with None Loose None Tightened. wire.

fan on. connection. A-239282.

04/06 90 2-RE-90-106C Alas with .None Closed valve. None Opened valve. -A-248351.

valve opened.

04/27 68 1-LT-68-325C Verify cal of None Seat table None Recal. A-247696.

xatr. leak.

4 04/27 68 1-LT-68-326C

~

Verify cal of None- Seat table 'None Recal. A-247695.

y xatr. leak. Recal. A-247695 04/30 63 1-LT-63-179 Top off filled None Lost fill, None Top off. A-285329.

leg.

04/29 68 1-PT-68-334 Verify cal of None Seal table None Recal. A-285328.

xatr. leak.

04/30 68 1-P'l 337C Verify cal of None Seal table None Recal. A-247700.

xatr. leak.

04/30 68 1-PT-68-336C Verify cal of None Seal table .None Recal. .A-247699 xatr. leak.

! 04/29 68 1-PT-68-342C Verify cal of None Seal table None. Recal. A-247694.

xatr. leak.

INSTRUMENT MAINTENANCE

SUMMARY

FOR TIE MONTH OF APRIL 1984 Page 6 of 6 EFFECT ON SAFE NATURE OF OPERATION OF CAUSE OF RESULTS OF ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE 05/02 68 1-LT-68-335 Verify cal of None Seal table None Recal. A-285326.

xmtr. leak.

05/02 68 1-PT-68-340 Verify cal of None Seal table None Recal. A-285327.

xmtr. leak.

05/03 62 1-LCV-62-118 Vlv not oper None Doesn't drive None Verified proper operation.

properly. properly. A-282457.

L 704/12 03 1-LCV-3-156A Vlv wot.'t stroke. None Vlv doesn't None Replace blocking rectifier stroke from & recal. A-241048.

NCR.

04/23 61 2-TR-61-138 Alms when None Hi switch None Adjusted & recal switch.

recorder stops. hitting to A-282407.

switch.

04/23 68 1-TI-68-316 TI not None No problem None Verified cal no problem indicating. found found. A-247192.

m Plant Maintenance Summary (Continued)

Field Services Group

1. ;ECN 2780--Post Accident Samplina Facility (Unit 2)

Following the . unit I cycle 2 refueling outage, work continued on the HVAC system with. core drilling of the auxiliary building, elevation 714 floor and A-11 wall. Also, installing ductwork, hangers, dampers, and additional equipment continued. Two panels, L-567 and L-569, were raised off floor elevation. 'The mechanical workplan for the fire protection system is-being prepared lfor-the approval cycle. The electrical workplan investigation, preparation,' and ordering of materials for conduit, core drilling, and equipment installation is complete.

2. .ECN 5200 -'-Unit 1 Post Accident Sampling Facility Final mechanical and electrical modification work for the facility was completed this month. This work included completion of the following items: facility fire protection system, facility ventilation, HEPA filter housing drains and traps, sample tubing, heat trace installation, and the breathing air systems for the facility.

Post modification testing and repairs were completed sufficient enough for facility operation.'

3. ECN 5198--Unit 1 Technical Support Center (TSC)

The TSC electrical and instrumentation work was completed this month sufficient to declare the unit I facility hardware operable.

4. ECN'5198--Technical Support Center (TSC) (Unit 2)

The conduit installation on elevation 685 of the control building resumed following the unit.1 cycle 2 refueling outage and will be continuing.

Also, the modification of the existing status monitoring system (SMS) cabinets to facilitate.new interface equipment began.

5. .ECN 5106--Unit 1 Reactor Vessel Level Indication System The remaining work to install and test this system was completed this month during the unit I cycle 2 refueling outage. This work included:

capillary leak testing, vacuum testing, and filling; completion of the remaining electrical and instrument work; and system testing during unit heat up.

6. ECN 6055 Unit 1 RCS Wide Range Pressure Monitorins Cable pulling and terminations were c6mpleted this month to relocate the pressure transmitters to elevation 090 of the axuiliary building.

Instrument calibration and post modification testing were completed this month sufficient to place the sysem in service.

~

. . Plant Maintenance Summary (Continued)

Field Services Group (Continued)

/7. ECN 6055--Unit 2 Wide' Range Pressure Transmitter to the RVLIS Panel' Conduit installation has resumedlin the auxiliary building. Writting

-of the mechanical workplans is ready to begin.

8. 'ECN 5773--Pressurizer Power Operated Relief Valve All remaining pipe support work was completed this month to complete changeout of the pressurizer power operated relief-valves.

9.- ECN 5045--RCS Cold Overpressurization System The remaining electrical and instrument work for this modification was

completed this month as well as post modification testing.

10. ECN 5842--Auxiliary Feedwater Cavitating Venturi Final piping support work as well as post modification testing were completed this month during the unit I cycle 2 refuleing outage returning the auxiliary feedwater system to service with a cavitating venturi serving each motor driven pump.

.11.- ECN 5196--Primary Containment Wide Range Pressure Monitoring

[ All outstanding electrical and instrument work was completed this month i

and this system was placed in service prior to the unit I startup.

12. . ECN 5069--Feedwater Flow Element Service Flanges Pipe flanges were installed for feedwater flow elements 1-FE-3-35, -48,

-90 and -103 in order to enhance service for these componenets. The i .- flow elements were reinstalled this month. Hydrostatic terting was j ,

conducted after the feedwater flow element instrument tubing was reconnected. -

13. ECM 5197--Unit 1 Reactor Vessel Vent fystem Final electrical installation work and the remaining pipe supports were installed during the month. Post modification testing was completed during unit I startup after the cycle 2 refueling outage.

14 ECN 5194--Particulate, Iodine, and Noble Gas Effluent Radiation

! Monitoring Facility The remaining electrical, mechanical and instrument work for the unit I facility was esmpleted thit, month sufficient to place it in service.

, Some electrical work remains for the unit 1 facility communication and security.

c Plant Maintenance Summary (Continued)

Field Services Group (Continued)

.15 . ECN 5024--Steam Generator Layup Recirculation The unit 1 piping tie-ins to the steam generator blowdown, chemical addition and. main feedwater systems were completed this month as well as their associated pipe supports, heat trace, and insulation.

-The unit 1 portion of this modification is complete.

16. .ECN 5939--Main Feedpump Turbine Condenser Retubing Restoration of the associated piping and piping supports was completed for.the unit I portion of this modification.

'17. ECN 5856--Pressurizer Loop Seal Drain Piping The unit.1' piping and pipe supports for this system were installed during refueling outage.

18.- ECN 5429--Hydronen Mitigation System Installation and post modification testing for four addition hydrogen igniters were completed during the refueling outage. -This modification is complete for unit 1.

19. Major Maintenance - Unit 1 Forced Outage Containment Decontamination - Due to failure of a high pressure seal on The RCS seal table, extensive decontamination of the incore instrument room, became necessary. This work was completed this month prior to repair of equipment in _the room.

Pressurizer Safety Valves - Two of the three subject valves were removed this month and will be replaced with two spare safety valves that are undergoing repair and testing.

1 i

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_ TENNESSEE VALLEY AUTHORITY Seguoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 MAY 151984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555

-Gentlemen:

Enclosed is the April 1984 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours,

~ TENNESSEE VALLEY AUTHORITY C. C.-Mason Power Plant Superintendent Enclosure cc (Enclosure):

Director, Region II Director, Office of Management Nuclear Regulatory Conunission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta Street Washington, DC 20555 (2 copies)

Suite 3100 Atlanta, GA 30303 (1 copy) INPO Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412

[ Palo Alto, CA 94304 (1 copy)

Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA 15230 (1 copy) 9\ 9 i i An Equal Opportunity Er. loyer