ML20097A115

Monthly Operating Repts for Jul 1984

ML20097A115
Person / Time
Site:	Sequoyah
Issue date:	07/31/1984
From:	Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8409130180
Download: ML20097A115 (24)

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TENNESSEE VALLEY AUTHORITY  ;

DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE

, NUCLEAR REGULATORY COMMISSION JULY 1, 1984 - JULY 31, 1984 UNIT.1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 1

Submitted By: .

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TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . I l

Significant Operational Events . . . . . . . . . . . . . . . . . 1-3 j PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . 3 Reports Licensee' Events . . . . .. . . . . . . . . . . . . . . . . 3-5 1 l

Diesel Generator Failure Reports . . . . . . . . . . . . . 5 l Special Reports . . . . . . . . . . . . . . . . . . . . . . 5

Offsite Dose Calculation Manual Changes . . . . . . . . . . . 5 Operating Data Unit 1 . . . . . . . . .. . . . . . . . . . . . . . . . . 6-8 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . 9-11 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . .- 12-21 I

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. Operations Summary July, 1984 The following summary describes the significant operational activities for the month of July. In support of this sunnary, a chronological log of significant events is included in this report.

Unit 1 Unit 1_was critical for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 831,710 MWH (gross),

resulting in an average hourly gross load of 1,117,890 kW during the month.

-There are 311.8 full power days estimated remaining until the end of cycle 3 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached August 3, 1985. The capacity factor for the month was 94.5 percent.

There were no reactor scrams, manual shutdowns, or power reductions during the month.

Unit 2 Unit 2 was critical for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 699,640 MWH (gross),

resulting in an average hourly gross load of 992,608 kW during the month. There are 25.9 full power days estimated remaining until the end of cycle 2 fuel. The cycle 2 refueling outage is scheduled to begin on September 7, 1984. The capacity factor for the month was 79.5 percent.

There were no reactor scrams, manual shutdowns, or power reductions during the month.

Significant Operational Events Unit 1 Date Time Event 07/01/84 0001 The reactor was in mode 1 at 100%

power producing 1120 MWe. An investigation was underway to determine the loss generation.

07/09/84 1438 Began reducing power due to both trains of auxiliary air out of se rvice.

1449 Held reactor power at 88%.

1458 Began power ascension.

1800 Reactor obtained 100% power, producing 1118 MWe.

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Significant Operational Events Unit 1 (Continued)

Date Time Event 07/31/84 2359- The reactor was in mode 1 at 100%

power producing 1118 MWe. 1The investigat ion continues to determine the loss of generation.

-Unit 2 Date Time Event 07/01/84 0001 The reactor was in mode 2 at 2%

reactor power. The outage continued for maintenance to feedwater valve 3-526.

07/02/84 1400 Began power ascension 1419 Reactor entered mode 1.

1509 The unit was tied on-line.

1627 The reactor obtained 30% power producing 176 MWe and holding due to steahn generator chemistry.

07/06/84 1404 Began power ascension.

2206 The reactor obtained 42% power and held due to feedwater chemistry.

07/07/84 0854 No. 3 heater drain tank pump A valve 5-540 had a broken stem.

1255 5-540 repairs completed, began power ascension.

07/08/84 1158 The reactor obtain 100% power producing 1144 MWe.

07/09/84 1438 Began reducing power because both auxiliary air compressors were inoperable.

1448 B train auxiliary air declared operable. Began power ascension.

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, ., Significant'Oparationel Evznto

-(Continued)

Unit 2 (Continued)

Date Time Event 1

7/09/84 1844 The reactor obtain 100% power

. producing 1145 MWe. ,

l 07/31/84. 0839 No. 2 throttle valve closed, the l reactor reduced to 98% power l producing 1121 MWe. )

l 0935 Began power ascension. i 1100 The reactor obtained 100% power producing 1136 MWe.

1605 Began reducing power due to the loss of_ coolant flow to the EHC.

1630 Held reactor power at 90% producing

'1070 MWe.

1655 Began power ascension.

2200 The reactor obtained 100% Power producing 1140 MWe, 2400 The reactor was in mode 1 at 100%

power producing 1140 MWe, 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 July 1984, to the Nuclear Regulatory Commission.

LER DESCRIPTION OF EVENT 1-84036 At 2115C on June 18,1984, unit 1 experienced a reactor trip.

Unit I was in mode 1 (2235 psig, 478*F) at 100% reactor power just prior to the event. A turbine trip occurred due to a gasket slipping and shorting the generator bus to gound. The electrical trouble alarm caused the turbine to trip and the P-9 interlock caused the reactor to trip. Unit I stabilized at 547*F following the reactor trip.

Licensee Events and Special Reports (Continued)

'LER DESCRIPTION OF EVENT 1-84040 A technical specification surveillance requirement (SR) for a

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standby. diesel generator was not performed within the required time. The SR was-to be performed.every 18. months to; check the diesel overspeed' trip lockout circuit., The part of the-procedure that performed this SR had been revised to make this SR a five year requirement. The procedure was.immediately revised and.the surveillance was performed. The diesel passed the surveillance,-and it was returned to service, 1-84041 The pressurizer pressure indicator in.the auxiliary co'ntrol' room (ACR) was discovered inoperable by the performance of a monthly surveillance instruction (SI). Upon investigation, Eit was discovered that a wire had been reterminated incorrectly the last time this indicator was calibrated. The wire was lifted, reterminated in the correct position, and the loop.

was returned to service. Since the ACR was not' required to be in use during this time, the indicator was not relied upon by personnel for the operation of the plant.

4 1-84042 Due to an incomplete modification, radiation monitor 0-RE-90-225 would not provide automatic isolation of direct releases from the neutralization tank. Two batch releases were made from the tank without compliance with action statement 30 of LCO 3.3.3.9.

1-84043 At 1000C on June 23, 1984, a thermal fire detector in the diesel generator corridor was determined to be inoperable during the performance of surveillance instruction (SI) 234.6, " Tech Spec Fire Detectors." A fire watch is required to be established within one hour and each hour thereafter until the detector is repaired. Due to miscommunication between personnel, the shift engineer (SE) was not notified that the fire detector was inoperable; therefore, the fire watch was never established. Maintenance personnel replaced the fire detector at 1502C on June 26, 1984.

2-84009 On June 30, 1984, maintenance was being performed on main feedwater pump (MFP) 'B' . MFP 'A' was in the reset condition.

The two motor-driven auxiliary feedwater pumps (MDAFP)'were running. MFP 'A' was accidentally tripped and generated an auto start signal (ESF actuation) for the auxiliary feedwater (AFW). The turbine-driven auxiliary feedwater pump (TDAFP) did not start due to flow control valve (FCV)-1-15, main steam supply, failing to close. FCV-1-15 was repaired and returned to service. There was no effect upon public health or safety, and no plant safety margins were exceeded.

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Liernten Evznts and Spacial Rtporta (Continued)

LER DESCRIPTION OF EVENT 2-84-010 This event occurred while unit 2 was in mode 1 (100% reactor power, 2235 psig, 578*F). Technical specification 4.6.3.4 requires each containment purge isolation valve to be-demonstrated operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of

-the. valve. Valves 2-FCV-30-9, -10, -52, and -53 were closed.

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at 2020 CDT on June IS, 1984 after an upper. containment purge

-and.were not tested until 1005 CDT.on June 20, 1984. The.

failure to test these valves was due to Operations failing to notify the Engineering Test Section that an upper containment purge had been completed. Upon discovery of this condition, the Engineering Teat Section was immediately notified, and the valves were tested per applicable procedures.

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

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

Offsite Dose Calculation Manual Changes There were no changes in the Sequoyah Nuclear Plant ODCM this month.

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. -OPERATING DATA REPORT

. DOCKET NO. 50-327 DATE AUGUST 7, 1984 COMPLETED SY M. G. EDDINGS TELEPHONE (615) 870-6248 OPERATING STATUS

1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:

2. REPORT PERIOD: JULY 1984

-3. LICENSED THERMAL POWER (NWT): 3411.0

4. NAMEPLATE RATING (GROSS MWE): 1220.6

-5. DESIGN ELECTRICAL RATING (NET MWE): 1148.O-

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0

-7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 G. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE-LAST REPORT, GIVE REASONSI-_--

-__ ----_--== - - _- -

, 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 744.00 5111.00 27048.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 2676.10 17117.66

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 744.00 2521.80 16634.95

15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2533527.07 7634988.97 53126839.27

-17. GROSS ELECTRICAL ENERGY GEN. (MWH) 831710.00 2499950.00 17879086.00

10. NET ELECTRICAL ENERGY GENERATED (MWH) 803282.00 2391807.00 17168735.00

19. UNIT SERVICE FACTOR 100.00 49.34 61.50 l20. UNIT AVAILABILITY FACTOR 100.00 49.34 61.50

21. UNIT CAPACITY FACTOR (USING MDC NET) 94.05 40.76 55.29

22. UNIT CAPACITY FACTOR (USING DER NET) 94.05 40.76 55.29

23. UNIT FORCED OUTAGE RATE O.00 32.74 20.60

-24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH)2

---

-_--__--____--_-- -=

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25. IF SHUTDOWN AT END OF RUPORk PERIOD, kSTIMATED DATE OF STARTUPI l

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

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q UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-327 UNIT NAME :Secunvah One DATE Aneust 9. 1984-COMPLETED BY M. Eddines- '

REPORT MONTH my TELEPHONE' (615) 870-6248-e-

- '5 7 "!: (( h Licensee- # Cause & Corrective No. Date ?_ t$ 8 iO5 Event [1 E% Action to.

1. 25 2 5y" Report # g] g *g - Prevent Recurrence 5" EdE &* 8*

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No Shutdowns or power reductions during month, h 9 1 2 3 - 4 -

F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain)- 1-Manual for Preparation of Data B-Naintenance 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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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT Seauovah one DATE Aunust 9. 1984

, COMPLETED BY- M. Eddings TELEPHONE (615)870-6248 NONTH JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,

1 1086.2 17 . 1077.5 2 1084.3 18 1100.5 3 1087.8 19 1079.2 4 1090.2- 20 1077.0

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5 ing7_o 21 1080.8 6 1082.7 22 108.&'. 2 7 1082.8 23 1077.8 8 1084.8 24 1077.3 9 1070.2 25 1077.0 10 1082.2 26 1074.0 11 1083.2 27 1074.0 12 1082.8 28 1064.8 13 1084.3 29 1077.0 14 1082.5 30 1075.2 15 1078.7 31 1069.2 ,

16 1079.0 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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OPERATING DATA REPORT DOCKET NO. 50-328 DATE AUGUST 7,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6248 OPERATING STATUS

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

2. REPORT PERIOD: JULY 1-31,1984 Item 23 YR-TO-DID and

3. LICENSED THERMAL POWER (MWT): 3411.0 Cumulative values are

4. NJMEPLATE RATING (GROSS MWE): 1220.6 corrected. The outage

5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0 in June was designated

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 a scheduled outage.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 O. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST PEPORT, GIVE REASONS:

- -- .-. __- =-

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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 744.00 5111.00 19008.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 5035.40 15396.47

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 704.85 4959.07 15113.39

15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2105415.32 16351509.85 48769577.66 l 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 699640.00 5600290.00 16632230.00 l 18. NET ELECTRICAL ENERGY GENERATED (MWH) 673665.00 5397464.00 16015201.60 l 19. UNIT SERVICE FACTOR 94.74 97.03 79.51 1

20. UNIT AVAILABILITY FACTOR 94.74. 97.03 79.51 l 21. UNIT CAPACITY FACTOR (USING MDC NET) 78.87 91.99 73.39

22. UNIT CAPACITY FACTOR (USING DER NET) 78.87 91.99 73.39

23. UNIT FORCED OUTAGE RATE O.00 1.87 6.96 l 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS ~(TYPE, DATE, AND DURATION OF EACH):

.Kefus11.DELhd.ifi Aat_ ion Cyp _le 2 September e _72 1984 5 7 d_am__

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

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

_9_

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0 0 50-328 UNIT NAME Sequovah Two DATE August 7, 1984 . .

COMPLETED BY :D. C. Dupree

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REPORT MONTF. JULY TELEPHONE- .(615) 870-6248 N

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_ @g e c yt Licensee y Cause & Corrective Wo. Date E O$ @ ]O2 Event 5% Ei, Action to y 2j g ~y" Report ? M~8 &? Prevent Recurrence E~ "

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5 840701 S 39.15 B 4 . Ffanually shutdown to repair feedwater drain valve 3-526. Reactor at 2%.

1 2 3 -

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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

'- &.I AVERAGE DAILY UNIT POWER LEVEL'  !

DOCKET No. 50--328

-UNIT Sequoyah Two.

DATE' -August 7, 1984

, COMPLETED BY- 'D. C. Dispree TE5EPHONE- (615) 870-6248' MONTH JULY DAY AVERAGE DAILY POWER LEVEL DA AVERAGE DAILY POWER LEVEL ~

'(MWe-Net)' -(MWe-Net) ,

-1 0 17 . .1103:

2 231 18 1105 -

3 9 c,1 19

. 1106 4 -

259 20 1106 5 254 21 7 l'.106

-6 297 22 .1166'. -

7 506 23 .1108 8 1042 24 1103-9 1102 25 1101' 10 - 1109 26 1097 11 1107 27 1098-12 1107 28- 1101 13 1106 29 1101 14 1106 30 1102 15 1105 31 1087 , ,

16^ 1105 INSTRUCTIONS .

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

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..' . Plant-Maintenance Summary =

(Theffollowing'significant' maintenance items were completed during the

-month of July.1984:

Mechanical Maintenance-

1. Replaced the bonnet on 2-VLV-3-524 and injecte'd the drain line with furmanite to stop the leakage. Furmanited several valves'on both units on. systems #1, 3, 5, &-6. . These-were both CSSC and Non-CSSC valves.

2 3. Repaired a bent stem on 2-LCV-6-106A.~

3. - Replaced a broken linkage that engages the turning gear on the unit 2 main turbine.

54. After being cut in half, the "2A" mixed bed demin tank was welded back

'together and the welds.x-rayed. Indications were ground out and rewelded.

Piping to the tank were welded back and some welds were x-rayed. All welds subsequently. passed the x-raying.

-5. The "2D" cooling tower lift pump was pulled, all bearing and one sleeve were replaced, and the pump was reinstalled.

6. Two Allis-Chalmers pumps were installed in the location of the boric acid evaporator "B" concentrate pumps.

7. Replaced a damaged motor on the 2A-A centrifugal charging pump.

8. Repaired the elevation 734 airlock on unit 2 reactor building.

9. "B-B" auxiliary air compressor was reported to be making a " knocking" noise. Gaskets were replaced on this compressor. "A-A" compressor was also dissassembled for maintenance and found to have a broken crankshaft.

The crankshaft was replaced and the compressor was completely rebuilt.

10. - Lubricated the coupling and aligned the IB-B containment spray pump.

11. Unplugged the sample line from the unit 2 gross fail fuel detector to the hot sample room.

12. Tightened the packing on the 2A-A and 2B-B motor driven auxiliary feedwater pumps.

13. Oil was added to 2-PCV-3-132 which controls the output pressure on the auxiliary feedwater pumps.

14. Replaced the' solenoid on 1-FSV-3-175.

15. Performed SI-102 on the 2A-A diesel generator (annual inspection).

ELECTRICAL MAINTENANCE Page 1 of 2 DATE. C0rPOENT... . . FAILLNtE DESCRIPTION,..... CAUSE OF FAILLNtE......... CORRECTIVE ACTION........- PROB.... ,

06-13 2-fRRB-030-003 CONTAINENT AIR RETURN BADAGASTAT TIrER REPLACED TIfER Ale SET- M 9-B -

TITER ON 2B2-9 4B0 VOLT FOR 10 MINUTES CECNED .' .

SHUT DOW BOARD FAILED TIFER Am RETURED TO ACCEPTANCE I&lILE' SERVICE PERFORMING SI28 .

06-14 1-fRRB-313-JE/ OIL LOW Ale FREON LOW OIL Ale FREON LIES REPAIRED LEANS Ale ADDED IEE 11D-A SLEWING ON GAGES ON 4B0 LEAKING 1.5 GAL OF 4GS DIL AW VOLT BOARD ROOM CHILLER FILLE 0 TO PROPER LEVEL s 1A WITN R-22 FREON 06-14 2-f4RB-030-045 DIESEL GENERATOR 2A ROOM DArpER FIOTOR BAD STARTER REPLACED MOTOR STARTER NOE 2A-A EXHAUST FAN 24-A CONTROLS WIleING SHORTED OUT DAf9ER tt0 TOR AND CRYDON KEEP BLOWING FUSES RELAY PER MSAI 12 06-21 1-CCRP-082-000 ALARtl HORE ON PAELOF HORE DEFECTIVE REPLACED NORN Ale IE E 1B-B GENERATOR 18-B CONTROL PERFORrE0 MI6.20 Ale M8AI l BOARD DOES NOT WORK 12 OPERATIONS PERFDRfED i SI 7.1 07-04 2-BCTD-001-001 FIOTOR TERtlAL DVERLOADS PROBABLE CAUSE WAS SURGE BRIDGED Ale FEGGARED NOE 5-A KICKING OUT ON BOARD ROOM IN POWER OWRLOADS FOR PROPER SIZE f.L 2A2-A/19A U(2) EST VALVE PER SI 251.2 EVERY THIPG

!Y ROOM ISOLATI(Di VALVE CECKED OK '

2-FCV-1-15 i

! 07-06 2-BDB-201-DN-A LIGHT GOES OUT ON 4B0 C-PNASE WAS SIEWING DEAD CECEO GROLAG I)CICATERS NONE j VOLT SleTDOL41 BOARD 2A1-A GROUle PROBABLE CAUSED SEVERAL TIES NO GROUND IN AUX BUILDING WEN FROM I!9 ROPER WAY OF COULO BE LOCATED CLEANED

! GROUlO DETECTS ARE PUSED PUSHING IN ON THE GROUlO AM) REIURED TO SERVICE DETECT 1 07-07 1-ENB-082-000 PUSN BUTTON TEST SWITCH CONTACTS BAD ON POLER REPLACED POWER ON RELAY NOME 1A-A DOES NOT WORK EACN TIfE RELAY CHECKED At#UCIATION IT IS PUSED ON LIGHTS Als RELAY DIESEL

, AlHJICIATION CONTROL GEERATOR WAS NOT i POER FAILURE BLOWN FUSE INOPERABLE AT ANY TIFE i 07-11 0-LWR 8-311-017 AIR BtNIBLES IN SIGNT AIR IN REFRIGEENT GAS CECKE0 PRESSURE IN SIGIT NONE i 18-B GLASS tlABE LOW ON FREON GLASS OPERATING PROPERLY j AT THIS TIFE I

07-11 0-ffTRB-311-017 AIR BUBBLES IN SIGHT AIR IN REFRIGEENT GAS CECNED PRESSURE IN SIG{T NONE i

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ELECTRICAL MAINTENANCE Page 2 of 2 DATE. C0rPONENT..... FAILIAtE DESCRIPTION...... CAUSE OF FAILtRE......... CCRRECTIVE ACTION........ PRON....' .

18-9 GLASS f1ABE LOW ON FREON GLASS OPERATING PROPERLY 07-15 1-25-062-0144 OPEN LIf1IT ON f1ANE UP VALVE ON f1ANE UP CHARGING VALVE OPENED AND CLOSED NOE CHARGING PLR1P WILL NOT PLFP UILL NOT FULLY CLOSE PROPERLY WITN A CLEAR POSSIBLE FR0ft CORROSION FUlCTIONAL TEST STATUS OR RUST LIGNTS CORRESP0leED TO VALVE POSITION 07-16 1-BATA-082-UC- CELLS 54 AFD 25 IN DIESEL STRAP C0l#ECTIONS CLEAfE0 Ale RETOReUED NUE B GDERATOR BATTERY IB-B

, CORRODED NO DIRTY AFD C0!tECTIONS PERFORIED St ARE READINGIN EXCESS OF LOOSE 238 READINGS ARE 150X10/6 OlftS ACCEPTABLE i

4 11 scords Iisted.

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Plant Maintenenca Summ ry

-(Continued)

Instrument Maintenance

1. During th'e month, five containment vent isolations occurred. Four of the five were on unit 2. These occurred during the first part of the month before time. delay relays were installed (ECN 6095) in radiation monitoring circuits. The relays will present inadvertant actuation from spurious EMI which occurs in the detector signals. l

2. The monthly calibration check of the UHI level switches on both units

.found all switches except 2-LS-87-22 within Tech Spec tolerance (reference PRO 2-84-107). DCR P-2111 is being processed to replace the Barton Model 288A switches with a more reliable instrument.

3. Unit 1 Post Accident Monitoring wide range reactor coolant system pressure channel P-68-69 was changed from 0-600 psi to 0-3000_ psi by TACF 1-84-83-68.

The 0-3000 psi indication for this channel was replaced during the refueling outage leaving only the 0-600 psi indicator as the PAM 2 channel (reference PRO l-84-276). An FCR to' ECN 6055 is being prepared to add another wide range indicator so the narrow range indicator can be returned to its original range.

4. Unit 2 P-250 computer was out of service most of the day on July 23, 1984.

Problems were encountered with the random access disk memory (RAD) controller. Four circuit cards were replaced and a disk head was spared out. Additional diagnostic testing is planned during the upcoming refueling outage.

5. Unit 2 throttle valve no. 2 drifted close on July 31, 1984. During_a transient on the EHC oil system, an EHC oil pump failed. The high pressure filter, an unloader valve, and both oil pumps were replaced. The no. 2 throttle valve remains closed and replacement of the Hoog Servo on the dump valve is planned during the upcoming refueling outage.

6. Other maintenance work is shown on the attached list.

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INSTRLTENT MAINTENANCE

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INSTRtfENT MAINTENANCE F10HTHLY Surt1ARY 08-08-84 PACE 1 C0rp MR.C0rP U FUNC SYS ADDRESS. DATE. . . . DESCR IPT ION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCRRECTIVE ACTI0H. . . . . . . . . . . . . . . . . . . . . . . - -

2121290 2 FIS 074 24 07/13/84 2-FIS-074-24, GAUGE FLUCTUATES (BOUNCES) FROM THE FLOW IPOICATOR SWITCH WAS FOUND OUT ,

0-900 GPM UITH PUrP RUtNING.. CECK CALIBRATIO4 0F CALIBRATIDH. REC 4 IBRATED TtE SWITCH

• MO PROPER OPERATION OF GAUCE. NO RETURNED TO SERVICE.

A233371 2 LT 063 176 07/06/84 2-LT-063-176, CHECK CALIBRATION A CALIBRATION CHECK IAS REGUESTED DUE TO THE TEST EQUIPMENT U!ED BEDE OUT OF CAL. DATE. VERIFIED CALIBRATION #D RETURNED TO SERVICE.

A238678 0 PS 032 88 07/09/84 0-PS-032-88,RECALIBRATE INSTURf1ENT TO 80 PSIG A REQUEST WAS MADE TO LOWER THE OECR INSTRUrENT FR0n 84 PSIG TO 80 PSIG DE TO TE PRESSURE OPERATED RELIEF VALUES BEING SET AT 80 PSIG. RECALIBRATED THE SETPOINT AND RETURED TO SERVICE TACF N0-84-79-32.

2238679 0 PS 032 62 07/09/B4 0-PS-032-62,RECALIBRATE INSTRtJ1ENT TO 80 PSIG A REQUEST WAS T1ADE TO LOWER THE DECR INSTRUMENT FR0ft 84 PSIG TO 80 PSIG DUE TO TE PRESSURE OPERATED RELIEF VALVES BEING SET AT 80 PSIG. RECALIBRATED TE SET POINT #O RETURNED TO SERVICE.

TACF #0-84-79-32 A238767 1 TI 068 44 07/18/841-TI-068-44E,HAS FAIL - INVESTIGATE NO CORRECT. TE TErPERATURE INDICATOR WAS FAILING DUE TO TM-68-44P, TM-68-449 BEIts OUT OF CALIBRATION. REC #_IBRATED 1 '

TM-68-44P, TM-68-4E, AND TM-68-440, VERIFIED OPERATION #O RETUREO TO SERVICE.

L'38800 1 LEV 003 171A 07/24/841-LCV-003-171A,LCV-3-1A WILL NOT C0tE FM.LY THE CURRENT TO PRESSLRE TRANSDUCER WAS OPEN. INVESTIGATE AND CCRRECT CAUSE OF F0ut0 HAD DUF TO CYCLIC FATIGUE.

t1ALFUNCTION. REPLACED T E TRANSOU R. CALIBRATED, VERIFIED 00ERATION, #O RETURNED TO SERVICE.

A239274 2 LI 068 312C 07/02/84 2-LI-068-312C,DDICATItC 58% WITH CR I!OICATING THE LEVEL TRANSMITTER WAS FOUND OUT OF AT 64%. CALIBRATION DUE TO NATURAL CAL. DRIFT.

RECALIBRATED THE TRMB1ITTER AND RETL'RtED TO SERVICE.

A239316 2 LI 068 300 07/02/34 2-LI-068-300,f1CR INDICATES HIGHER THAN ON INVESTIGATION THE LEVEL TRANSi1ITTER DOICATING IN AUX. CONTROL Rft. WAS FOUND OUT OF CALIBRATICH DUE TO NATURAL DRIFT. RECALIBRATED TE TRANSMITTER BACKFILLED #O BLED THE SENSOR BELLOWS AND RETURED TO SERVICE.

A239864 1 PS 003 07/27/841-PS-003 , VERIFY CAL. OF SWITCHES, r1AKE REPAIRS TME SWITCH L%S FOUND IN0pERABLE.

NO ADJUSTMENTS, REPLACE SWITCHES IF ECESSARY. XERCIZE0 TFE SWITCH, RECALIBRATED,

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INSTRUMENT MAINTENANCE INSTRtdENT F1AINTENANCE T10NTHLY SUmARY 08-08-84 PACE 2 CORP '

MR.ConP U RJNC SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCRRECTIVE ACTICti. . . .. . . . . . . . . . . . . . . . . . . -

VERIFIED OPERATION, #O RETtRNED TO ' ,

SERVICE.

A281658 2 LI 063 176 07/03/84 2-LI-063-176,CONTAIM1ENT Surp LEVEL IPOICATOR TFE SENSOR BELLOUS WOtE FOUND BAD OUE 10 READING 4% WITH NO LEVEL CYCLIC FATIGUE. REPLACED TFE BELLOUS, BACKFILLED THE SYSTEM RECALIBRATED APO '

, TIRE RESP 0tlSED AND RETURED TO SERVICE.

A282145 1 DS 003 1650 07/28/841-PS-003-1658, REPLACE BROKEN LUG ON HC2 BLACK THE LUG WAS FOUND BROEN TO THE PRESSURE Ato WHITE WIRE. SWITCH RESALTING IN A DEFECTIVE C0tfECTION. REPLACED TE LUG VERIFIED SWITCH CPERATION, AND RETURNED TO SERVICE. e A282978 1 LJ 063 179 07/10/84 1-LI-063-179, INDICATOR HAS APPEARED TO HAVE TFE 8ELLOUS IN THE LGEL TffANSMITTER FAILED OFFSCALE LOW. CECK CALIORATION WERE FOUPO BAD DUE TO CYCLIC FATIQUE.

REPLACED THE BELLOUS. FILLE 0 SYSTEtt, RECALIBRATED, ANJ RE1URED TO SERVICE.

A285345 1 PI 068 66 07/27/81 1-PI-068-66.RESCAE 1-PI-68-66 FR0f10 TO 600 TFE SYSTEN ENGINEER REQUFSTE0 A PRESSURE

/SIG TO 0-3000 PSIG. INCREASE FRC(1600 PSIG TO 3000 PSIG OH THE INDICATCR. INCRFASED TFE PRESSURE RANGE AND RESCALED TE ASSOCIATED PRESSURE F1001FIER.

A289541 2 LEV 003 156 07/11/84 2-LCV-003-156,POSITIOER NEEDS TD BE ADJUSTED. TtE STEtt CONNECTOR CLArp WAS LOOSE WHICH CAUSED TE LIMIT SWITCH ACTUATER ARM TO BEHO CAUSING FECHANICAL DAMAGE.

g TIGHTENED THE CLArp, REPAIRED THE LIMIT i SWITCH ARM, VERIFIED VALVE STROKE, APO RETURNED TO SERVICE.

289678 1 LT 063 99 07/30/84 1-LT-063-99,LI HAS FAILED HI TIE TRANSMIITER HAD A HIGH OUTPUT DUE TO CALIBRATION DRIFT. RECALIBRATED TE TRANSMITIFR AND RETURNED TO SERVICE.

292046 1 LEV 003 148 08/03/841-LCV-003-148.TE VALVE IS LEAKING THt00GH. TFE RELAY WAS FOUND LEAKING OH TE VALVE stFRDu POSITIONER. kEDLACED TE RELAY APO VERIFIED THE STROKE #0 RETURtED TO SERVICE.

4293095 0 RM 090 206 07/25/84 0-RM-090-206, RAD FDlITOR IS SHOWING 0 COUNTS. TIE f10 nil 0M WAS SHOWING 0 COUNTS DUE TO INVESTIGATE AIO REPAIR AS HECESSARY. HAS A LOOSE PLUG. TIGHTDED TFE PLUG ,

MALFUNCTION ALARM IN CH 0-n-12 VERIFIED OPERATION AM) RETURED TO SERVICE.

293096 0 Rri 090 141 07/25/84 C-RM-090-141, RAD FD4ITOR FOR ERCW 0-RM-90-141 TIE RAOIATION r10 nil 0R HAS FAILED LOW DE HAS FAILED LOW WITH NOT ANY POWER IlOICATIONS. TO A BAD POWER SUPPLY. REDLACED TE POWER SUPPLY WITH A SARE LMICH WAS REPAIRED ON AHOTHER rR.

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. Plant Maintenance Summary (Continued)

Modifications Group

1. ECN 5237- Laundry Facility The work on the HVAC continued. The duct work was completed except testing and completion of the air plenum around the dry cleaners. Work on the

-chiller package continues.

2. ECN 5596 - Batch Neutralization System The access platform was completed. Heat trace functional testing to be performed when pipe insulation is completed.

3. ECN 5645 - Steam Generator Blowdown System - Unit 2 All pre-outage piping fabrication is complete. Instrumentation installation continues. Conduit work and cable pulling continues.

4. ECN 2768 - Reactor Pressure Vessel Level Indication System (RVLIS) (Unit 2)

Writing and approval of four mechanical workplans was1 completed. Two .

workplans remain in the approval cycle. Pre-outage work has started on two workplans. HVAC work continued and is 90 percent complete.

Miscellaneous tubing work was performed. The fire protection for the room was completed except tie-in hydro.

Installation of conduit outside containment. began. -The preparation of the work plan for cable pulling and cable termination continued. The procurement.for all electrical materials continued. The preparation of the workplan for inside containment is in progress. Rework of existing conduit cables over 2-R-148 are complete awaiting support from instrument maintenance to verify operability of loop 68-398.

5. ECN 6055 - Wide Range Pressure Transmitter to the RVLIS Panel Mechanical workplan writing is in progress. Conduit work continues. Cable pulling and termination workplans are being prepared. ENDES and instrument maintenance are making changes to the unit 2 control room indicators.

6. ECN 5194 - Iodine Monitoring Building Mechanical work is complete with exception of the control air tie-ins which are scheduled for the unit 2 cycle 2 refueling outage. Conduit and cable pulling is in progress.

7. .ECN 5024 - Lay-up Water Treatment Pre-outage fabrication .of piping was started. Core drilling of the air intake room was completed. Construction continues their prefabrication activities associated with the pumps.

C- Plant MaintenanceLSummary (Continued)

Modifications Group

(Continued)

8. -ECN 5009 - ERCW Piping Change-Out-Prefabrication of piping for the installation of ~ stainless steel pipe ~ for the' centrifugal charging pump room coolers was started. Installation is

planned for'the unit 2 cycle 2 refueling' outage.

9. ECN 5202 '-~ Interfacing the Diesel Generator Buildings -and the Power House .

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Workplan preparation was started-for the ERCW tie-ins required for the diesel generators.

10. ECN 5842 - Replacement of PCV-3-122 and -132 Workplan preparation and approval- was completed for hangers. ' Wo rk implementation-is scheduled for unit 2 cycle 2. refueling' outage.

E. ECN 5938 - Feedwater Heater' Tube Change-Out Work was completed on pre-outage work' involving platforms and rigging devices. Workplan preparation and approval was completed.

12. NUREG 0588 ECN L5457 Solenoids were changed out. Remaining items are scheduled for the outage.

ECN L6090 Installation of quick exhaust. valves was completed.

ECN L5895 .Workplan preparation and approval was completed.

ECN L6032 Workplan preparation and approval was completed.

ECN L5883 Workplan preparation and approval was completed. The workplan remains in the approval cycle. '

ECN L5881 Workplan approved. Work began on fabricating brackets for limit switches.

ECN LS823 Workplan approved. Awaiting craft support.

ECN L5383 Flow switches and press switches workplans in preparation.

ECN L5824 One workplan for valve operator replacement has been completed and two to 125 valve operators have been replaced.

ECN L5370 Workpaln 10617. - 15 of 16 motors replacea. Sixteenth ~ motor is awaiting repair or to be transferred in from Hartsville.

Flow transmitter for L5884 has-been reordered and workplan 10777 is in

-approval cycle.

13. ECN 6182 Workplan preparation was started and contractor scheduled to arrive during August.

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ .2. .- _ _--

.- Plant Maintenance Summary (Continued)

Modifications Group.

(Continued)

14. ECN 5664 - Wells Fargo AS-24 Cards Relay Change-Out Field ' work on the boxes is approximately 65% complete. CAS/SAS j terminations'Is 10% complete. -Cable pulling is in progress.

'15 . ECN 5172 & 5968 - Emergency Lighting-SDFWP, AFP, FW REG VLVS and MS Power Operated Relief VLV Areas Installation'of new conduit, strobe lights, and sirens continued.

Estimated completion of WP 10578 is around mid October if worked during upcoming unit.2 coutage. '

- 16. ECN 5770 - Installation of-New Rad Monitor in the Condenser Exhaust

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i Fifteen of sixteen complete. Awaiting repair or replacement of the 16th.

17. ECN 5867 - Unit 2 Spend Fuel Transfer System Westinghouse modifications are complete on the pit side and work has commenced on the reactor side.

18. ECN 5871 - Relocation of the ERCW Rad Monitor "B" Train ERLW Rad Monitor is in service. "A" Train work is completed.

Instrument m intenance is expected to be complete by August 10, 1984.

19 .' ECN L2780- Post Accident Sampling Facility Unit 2 The conduit work outside containment is approximately 98% complete.

Cable pulling is approximately 65% complete. Cable termination began this period. Internal PNL wiring in various PNLs has begun and is approximately 40% complete.

20. ECN L5198 - Technical Support Center (TSC) Unit 2 Modification of the status monitoring system (SMS) cabinets has been completed. The control building conduit installation on elevation 685 continued and should be completed by mid August. DPM 50 and P250 tie work is continuing as well as cable installation.

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' TENNESSEE VALLEY AUTHORITY'

.Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy,-Tennessee. 37379

.Augustr14,'1984-Nuclear Regulatory Commission Office of Management-Information-and Program Control

. Washington, DC- 20555 Gentlemen:

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

Very truly yours, TENNESSEE VALLEY AUTHORITY GR.Aum P. R. Wallace Plant Manager Enclosure cc (Enclosure):

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

Suite 3100 Atlanta,- GA 30323 (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 (I copy)

Mr..R. C.'Goodspeed MNC 461 Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA -15230 (1 copy) 1' I \

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. An Equal Opportunity Empfoyer