ML20099J984

Monthly Operating Repts for Jan 1985

ML20099J984
Person / Time
Site:	Sequoyah
Issue date:	01/31/1985
From:	Dupree D, Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8503200133
Download: ML20099J984 (33)

Text

853 850215 988 l TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAll NUCLEAR PLANT MONTIILY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION

{

January 1, 1985 - January 31, 1985 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 l

UNIT 2 DOCKET NUMBER 50-32C LICENSE NUMBER DPR-79 Submitted by:

l

['7 P. R. Wallace, Plant Manager BB8agggygggagg7 jy, r,

t -o d

I TABLE OF CONTENTS gage Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . I Significant Operational Events . .. ..... . .... ... ... 1-4 i

PORVs and Safety Valves Sn= mary. . . . .... .. ... ...... 4 Reports Licensee Events . . . . ......... ..... ...... 5 l

Diesel Generator Failure Reports. ... . ........... 5 Special Reports . . . . .... .... . ..... ...... 5 Operating Data o

Unit 1. . . . ... . . . . . . . . . . . . . . . . . . . . . . . 6-8 1

Unit 2. . . . . . . . . .... . ... ............ 9-11 i

Plant Maintenance Summary. . . . . . . . .. . ..... .... .. 12-30 f

f

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

Operatien, Summary January 1985 The following summary describes the significant operational activities for the month of January. In support of this summary, a chronological log of significant events is included in this report.

Unit 1 Unit I was critical for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 862,250 MWH (gross), resulting in an average hourly gross load of 1,158,938 kW during the month. There are 139.9 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 July 16, 1985. The capacity factor for the month was 98.0 percent.

During the month, the unit experienced no reactor scrams, manual shutdowns, l or power reductions.

Unit 2 Unit 2 was critical for 718.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, produced 679,040 MWH (gross), resulting in an average hourly gross load of 967,018 kW during the month. There are 337.6 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 March 5, 1986. The capacity factor for the month was 77.2 percent.

During the month, the unit experienced two reactor scrams, one manual shutdown and one power reduction.

Significant Operational Events Unit 1 Date Time Event 01/01/85 0001 The reactor was in mode 1 at 100% power producing 1165 NWE.

01/06/85 1158 The unit has operated 100 days since the last turbine start-up. This is unit one's first 100 day run.

, 01/28/85 1545 B1 waterbox was removed from service to investigate for a tube leak.

1845 B1 waterbox was returned to service, no leak found 01/29/85 0140 B2 waterbox removed from service due to a tube leak.

01/30/85 1130 B2 waterbox returned to service.

01/31/85 2359 The reactor was in mode 1 at 100%

power producing 1180 MWE.

Significant Operational Events (Continued)

Unit 2 Date Time Event 01/01/85 0001 The reactor was in mode 1, holding at 30%

power due to secondary chemistry and producing 300 MWE.

0910 Began reducing power for the turbine overspeed trip test.

1127 The unit was removed from the power grid.

The reactor was maintaining 10% power.

1737 The unit tied on-line.

1930 The reactor obtained 30% power and was holding due to secondary chemistry. The unit was producing 318 MWE.

01/02/85 1245 Began power ascension.

1845 Stopped the power ascension at 42% power to investigate problems with the #3 heater drain tank pumps (3HDTPs).

1919 Resumed power ascension.

2354 Held 48% power for additional maintenance on the #3HDTPs.

01/03/85 0139 Resumed power ascension.

0800 Stopped the power ascension at 58% power to replace a leaking gasket 2B #3HDTP.

1050 2A and 2C #3HDTPs tripped due to problems with 2-LCV-6-106A and 106B. Began reducing '

power for maintenance on the valves.

1340 The reactor was maintaining 50% power.

01/04/85 1215 Began power ascension 01/05/85 0200 The reactor obtained 75% power and was holding while flux mapping and incore/excore calibrations were being performed.

01/06/85 1830 Resumed power ascension.

2

~

Sianificant Operational Events t

, , (Continued)

Unit 2 Date Time Event 01/07/85 0030 The reactor obtained 90% and held while l SI-78 was being performed.  !

l 0152I/ Began power ascension 1318 Maintained 95% reactor power for adjustments to the NIS channels.

, 1456 The reactor obtained 100% power and was i producing 1184 MWE. l 01/08/85 2326 All three #3HDTPs tripped. The operator performed a manual runback to 81% power.

The pumps were restarted.

2350 The #3HDTPs tripped again. The unit experienced e an auto runback to 78% power.

01/09/85 0315 Began power ascension.

0626 The reactor obtainad 89% power and was holding. Investigating 2-LCV-6-106A and 106B.

1001 Began reducing power to 80% for maintenance on 2-LCV-6-106A and 106B.

1206 The reactor obtained 80% power.

01/10/85 0932 Began increasing power.

5 1700 Thereactorobtained100%Nowerandwas producing 1184 NWE.

01/12/85 0320 2-LCV-6-106A failed.

0327 All three #3HDTPs tripped '

0328' NFPT-2A tripped due to the lost of injection water.

0329 The reactor tripped due to a lo-lo level in steam generator #2.

4 2154 The reactor was taken critical.

01/13/85 0354 The unit was tied on line.

0700 The reactor obtained 30% power and

! was holding due to secondary chemistry.

3

i Sinnificant Operational Events (Continued)

Unit 2 Date Time Event 01/14/85 0704 The reactor tripped due to the 2 of 4 logic of the NIS power range instruments.

i Instrument maintenance was performing SI-80 .

and when N-42 was returned to service the negative rate trip was not reset. When N-41 4

was removed from service 2 of the 4 channels were out-of-service, therefore the reactor tripped.

1428 The reactor was taken critical.

1826 The unit was tied on-line.

2025 The reactor obtained 30% power and was holding due to secondary chemistry.

01/16/85 0245 Began power ascension.

2140 The reactor obtained 100% power producing 1166 MWE.-

'; L 01/17/85 0004 2B #7HDTP tripped on motor overload.' /d Power was reduced and stabilized at 98% power.

0204 Increased power to 100%.

I

, 01/31/85 2359 The reactor was in mode 1 at 100% power >

j producing 1180 MWE. ,

,1 PORVs and Safety Valves Summary

! No PORVs nor safety valves were challenged during the month.

J ti j 4 t

Licensee Events and Special Reports The following licensee event reports (LER) were sent during January 1985 l to the Nuclear Regulatory Commission. ,

LER DESCRIPTION OF EVENT ,  ;

1-84070 During the performance of Surveillance Instruction (SI) 3 on December 24, 1984. Containment isolation valves 1-FCV-61-110 and 112 failed to stroke to the fully closed position. These t valves are the inboard and outboard isolation valves for the ice condenser glycol system. The outboard valve was manually closed to comply with the action requirements of LCO 3.0.3 and 3.6.3b.

1-85002 Following additional inspection of various safety-related systems, three conduits were found to have missing or damaged KAO-wool insulation; therefore, the conduit were not in compliance with Appendix R of 10CFR50. . The conduits (2PM1001I, 2PM1084I, and 2PN2114II) carry cables for steam generator pressure and flow transmitters and auxiliary feedwater flow transmitters.

Fire watches previously established in this area satisfies requirements of the action statement LCO 3.7.12.

1-8500-3 A review of a completed surveillance instruction (SI-233) performance package. " Visual Inspection of Penetrations, Fire Barriers, and Fire Stops" discovered that the SI performance had exceeded the technical specification maximum allowable performance date by 52 days.

2-84020 At 0826 CST on December 16, 1984, unit 2 experienced an inadvertent "A" train safety injection and a reactor trip.

Unit 2 was in mode 3 at the time of the injection and trip.

i 2-84021 During a load reduction to perform a main turbine overspeed tent, a reactor trip occurred at 1532 CST in December 29, 1984 on a loop 4 low-low steam generator level. The reactor was in mode 1 at 18% power.

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

I e

i Special Reports 84-11 On December 19, 1984, Operations Personnel were notified by TVA Office of Construction personnel of a failure to close a fire penetration ,

j breach within the allotted seven days in accordance with technical ,

l specification L.C.O. 3.7.12, action 'a' . The penetration, a three l inch mechanical pipe sleeve into the fifth vital battery room, was j breached at 1400 CST on December 11, 1984, in accordance with procedure l PHYSI-13, Attachment F, and closed at 0900 CST on December 19, 1984.

5

- t OPERATING DATA REPORT l l

DOCKET NO. 50-327 DATE FEBRUARY 6, 1985 COMPLETED BY M. G. EDDINGS TELEPHONE (615) 870-6421 OPERATING STATUS l

1. UNIT NAME! SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES: 1 2.' REPORT PERIOD: JANUARY 1985

3. LICENSED THERMAL POWER (MWT): 3411.0

4. NAMEPLATE RATING (GROSS MWE)! 1220.6

5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)! 1183.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0

8. 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)t_-______

10. REASONS FOR RESTRICTIONS,IF ANY!-______________________

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 744.00 31465.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 744.00 21391.66

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 744.00 744.00 20852.95

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2532389.16 2532389.16 67210075.11

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 862250.00 862250.00 22598666.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 828152.00 828152.00 21709782.00

19. UNIT SERVICE FACTOR 100.00 100.00 66.27

20. UNIT AVAILABILITY FACTOR 100.00 100.00 66.27

21. UNIT CAPACITY FACTOR (USING MDC NET) 96.96 96.96 60.10

22. UNIT CAPACITY FACTOR (USING DER NET) 96.96 96.96 60.10

23. UNIT FORCED OUTAGE RATE 0.00 0.00 17.80

24. SHUTDOWNS SCHEDULED OVER NEXT 4 MONTHS (TYPE, DATE, AND DURATION OF EACH):

ICE..MEIGRING.,_ARRIL 97cl E l9 DAYS-_-___________________-_________________

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.

6

1

- - @_ 3 ant -l

, " TK T AI-18 ~ C ~~ "

ATTACHMENT 1 I k-23Yi{ Appendix A ,, ,

AVERAGE DAILY UNITPOWER LEVEL

' \ .

['i'.Page73of8'..R*V-[id#/2-2 FILE PACKAGE NO. 55 DOCKET NO. S0-327 l REPORT REQUIREMENTS ' ONE UNIT

, s' February 1, 1985

- i .

DATE

' M. C. Eddings COMPLETED BY l ~ '

$- TELEPHONE (615) 870-6421 I  !

t .

JANUARY  :

MON DAY AVERAGE DAILY POWER LEVEL DAY '-

AVERAGE DAILY POWER LEVEL (MWe-Net) . (MWe Net) 1 1119 37 1125

~

2 1117 1126 33 3 1116 1124 -

19 _ t 4 1122 1121 '

20 5 1120 33 1120 [

6 1122 1118 ,.

7 1121 1113 -

, 23 3 1122 y 1112 .

m.

9 1122 25

. 1110- -

10 1126 -

26 -

11 1126 1118 .

27 -

1121 1119 t,.

- 12 4 28

',7 L._

13 1125

y

1133

'.' 34- 1126 . *1f36 '

', t

.M .

u-15 1125 3,

H38 1 16 1126 u

q. .

.. INSTRUCTIONS - - -

• s., .

On this format list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole mesawatt. ~'

(9/77)

Mi

~

i l .

- 'S .

, O 7

\ .

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 ,;

UNIT NAME c. .m..s m. .o

" y.4,ol...i/ iens

DATE -(.

COMPLETED BY sM. c. kddinas 'l REPORT HONTH JANUARY TELEPHONE (615) 870-6421 ,

n1 i M u u ,

e, u y3 Licensee ,, g, Cause & Corrective

(

No. Date

". S* $ $g Event 3.g g .g Action to g

R yg 3 jg& Report ! gg o.g Prevent Recurrence H g v5 g_g .m a m.s f .

No shutdowns or power reductions during month cm i , .

,3

.~ .

1 2 3 4 .

, Fr. Forced Reason: Method: Exhibit G-Instructions j S: Schedo'.ed A-Equipment Failure (Explain) 1-Hanual for Preparation of Data B-Ha4ntenance 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 H-Other (Explabi) Exhibit I-Same Source (9/77)

• 1 l

l OPERATING DATA REPORT DOCKET NO. 50-328 DATE FEBRUARY 6, 1985 COMPLETED BY D.C.DUPREE TELEPHONE (615) 870-6627 OPERATING STATUS

1. UNIT NAME! SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTESt

2. REPORT PERIOD! JANUARY 1985

3. LICENSED THERMAL POWER (MWT)* 3411.0

4. NAMEPLATE RATING (GROSS MWE)! 1220.6

5. DESIGN ELECTRICAL RATING (NET MWE)! 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS NWE) 1183.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE)* 1148.0

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONSt____________

4

9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE)t________

10. REASONS FOR RESTRICTIONS,IF ANYt_______________________

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 744.00 23425 00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 718.20 718.20 17413.32

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 702.20 702.20 16972.38

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 ,

16. GROSS THERMAL ENERGY GENERATED (MWH) 2002236.38 2002236.38 54001247.25

. 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 679040.00 679040.00 18370720.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 650071.00 650071.00 17671079.60

19. UNIT SERVICE FACTOR 94.38 94.38 72.45

20. UNIT AVAILABILITY FACTOR 94.38 94.38 72.45

21. UNIT CAPACITY FACTOR (USING MDC NET) 76.11 76.11 65.71

22. UNIT CAPACITY FACTOR (USING DER NET) 76.11 76.11 65.71

23. UNIT FORCED OUTAGE RATE 4.83 4.83 8.44

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

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt f

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

9

• ~ SGN9 - * -

, ';AI-18 ~T , ' ~~

.) ATTACHMENT 1 ..

I' i Appealix A

.' AVERAGE DAILY UNIT POWER LEVEL

, j- PageJ 3'of 8 '

,w. E*V'3.'.iM bE'

• FILE PACKAGE No. 55 DOCKET NO. 50-328 REPORT REQUIREMENTS ' WIT 2 g

DATE Februarv 6. 1985 ...

I i COMPLETED BY D. C. Dupree

' l . . .

i,. TELEPHONE (615) 870-6627 MONDg JANUARY

+ . . . .

4 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) . (MWe Net) 3 279 37 1130 2 335 gg 33x3 3 530 .g9 1144

! 4 574 20 1146 5' R77 1139 I 21 6 R45 22 ll39 ^

7 1117 1142 -

23 g 1140 y 1139 -

, 918 25

• II T

10 997 26 1147 _

II 1146 27 1144

. 12 I19 28 1147 u 1

. . .. 33 , 212 2, 1147 , . ...

34" 92 .

1141 .

• 30 - -

L_

IS 261 1148 3g _

16 756 a

[

. . MSTRUCTIONS - .

s.,

i On this format, list the average daily unit power levelin MWe. Net for each day in the reporting mimth. Compute to j ' the nearest whole megawatt. ~

, (9/774 ,

~ ~

MI

. g l .

• 10

_w _ -x. ~

, . '.' g n

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 ,

a UNIT NAME seauovah Two DATE February 6.1985 COMPLETED BY D. C. Dunree

• REPORT MONTH January, 1985 TELEPHONE (615) 870-6627

% u c, u y,o I.icensee . se En cause & Corrective ...

% S2 g .a j g Event 3g g,g Action to f

p y8 3 yg& Report i gg o. 3 Prevent Recurrence ,  ;

=

j5 A t,8 3c m g o

, Turbine Overspeed Test 1 850101 S 6.17 B 9 the reactor remained critical at 10% power All #3HDTPs tripped when 2-LCV-6-106A failed MFPT-2A tripped due to the loss of injection 2 850112 F 24.27 A 3 water and the reactor tripped due to Lo Lo level #2 steam generator.

~

• j l Negative. rate trip due to N.I.S. receiving a 2 out of 4 logic l signal shlle performing a 3 850114 F 11.27 B 3 maintenance instruction on N.I.S. '

'm 0

1 2 3 4 ,

F: Forced Reason: Method: Exhibit G-Instructions S:' Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation cf 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 H-Other (Explain) Exhibit I-Same Source (9/77) -

1

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____s

Plant Maintenance Summary The plant maintenance summary for significant maintenance items completed during the month of January 1985 are listed in the following order:

Construction Activities Electrical Maintenance Section Electrical Modification Section ,

Instrument Maintenance Section Mechanical Maintenance Section Mechanical Modification Section t

i i

12

Construction Activities 1 January 1985 ECN L5503, 5111 - Office and Power Stores Facility.

This project is approximately 96 percent complete. NUC PR occupied the top floor (EL. 740) on January 19, 1985. El. 726 is scheduled to be transferred to NUC PR on February 8,1985. Installation of doors, windows, office i partitions, electrical power cable and telephone cable (under carpet cables) continued. Scheduled-completion for this project is March 31, 1985.

ECN L5609, 5610 - Make-up Water Treatment Plant.

The project is approximately 75% complete. During this month, work continued on the installation of piping, cable trays, protective coatings, and yard piping. Installation of pump foundations in the Turbine Building continued.

Workplans for interfacing work in the Turbine Building have been approved.

The schedule for preoperational testing of the systems has been given to Construction to complete the systems required to facilitate pre-op so that

the plant can be operational by March 31, 1985. Construction may start

, multi-shift work on this building.

ECN L5599 - Fifth Vital Battery.

! The project is approximately 98% complete. Preoperational testiag of HVAC, F.P. and 5th vital battery testing began on February 2,1985. Installation of TCI insulation on the new conduit to comply with Appendix R requirement is in progress. High pressure fire protection tie-in point will be done during the U1 ice weighing outage. Protective coating in the room will be done after discharge testing is completed.

ECN L5841 - Hot Machine Shop

The project is 99 percent complete. Health Physics laboratory, deconning machines, electric shop, snubber shop, and hot machine shop are operational.

Work continued on communication and fire detection cable pulling and equipment installation. Monorail and hoist over the electropolishing equipment

in the decon room will be done later.

ECN L6182 - Cooling Tower Repair Custodis Ecodyne - The contractor finished ice damage related work on both cooling towers and left the site. They will come back later to complete the remaining two punchlist items (concrete louvers and nozzles).

Due to severe weather during January 20 through January 23, 1985 icing related damage occured to both towers. AtpresentEPApermittedSQNtogakeboth towers out of service until March 15, 1985, as long as a AT of 7 F is not l exceeded. This permission in granted to assess damage to the towers and remove debris from the base of the towers.

ECN L5202 - Fifth Diesel Generator Modification.

ERCW discharge piping in the yard being installed at present time.

13

, i.

• 06:37:34 02-06-85 ELECTRICAL ttAINTENAfCE FDmLY'REPGli FOR JAl0ARYB5 PA5E1 .

DATE.... GNF06ENT. . . . .

• FAIL 1RE DESCRIPTION...... CAUSE OF FAILtRE. . . . . . . . . CORRECTIVE ACTION........ . Pet.ND..

01-02-85 1-tfTRB-43H07 CONTAINENT AIR RETUtN le FAILURE RAN FtMCTIONAL TEST 2 A296729 ,

M FAN 15-8 DID MUT START TIES, FAN STARTED WITHIN WITNIN ALDTTED TIRE OF ALOTTED AMOUNT OF TITE 3

10+0R-1 MIMJTES 01-02-05 1-BATB-082 REPLACE NYDR0rETER IN ND FAILURE REPLACED NYDR0rETER AS A121925 1A-A DIESEL GEERATOR REGLESTED BATTEltY 4

01-03-95 2-HTCK-234 VERIFY PROPER OPERATION HD FAILURE FREEZE ret PERFORl1ED WORK PER A247638 0F T E E AT TRACE CIRCUIT INSTRUCTIONS ASSOCIATED WITH TE FEED WATER FLOW TRANBilITTERS CIRCUITS 405, 406,407,408,409,410,411 AIG 412 01-03-95 0-TC-234-300P TEFFERTURE CONTROLLER SET INSTRUNINATION FOLAG OPEN RECOP. DER lte! CATES 180 A239846 POINT IS 150 DEGREES F. TERT 10CUPLE ON POINT #16 DEGREES CONTROLLER IN AT

• RECORDER DOICATING 400 ON 0-TR-234-5004 195 DEGREES OUT AT 190 DEGREES F. TRANSFERED TO ELECTRICAL DEGREES CECNED FOR a CONTINUITY ON THERMDCtFt.E WORKING PROPERLY AT THIS TIFE 01-03i15 2-FCV-001-0011 ,BLLE LIGHT (M F1AIN STEAM LIttIT SWITCN STICMDC LUBRECATED LIrlIT SWITCH A289371 ISOLATION VALVE cores ON

, IAEN VALVE IS OPEN .

01-03-95 2-tmtt-072-000 CONTAINENT SPRAY EADER BAD FUTOR REPLACE 0 FIOTOR A291417 2 "B" WILL HDT WORK .

01-03-85 1-XA-055 LIFT WIRE NO 1f177 ON NO FAILURE LIFTED ADO TAPED WIRES A031298 BREANER N17 (M 120 VITAL AFC LEADS AS REGUESTED INSTRUPENT POER 80ARD 1-I, LIFT WIRE ND 1MB4 ON 9

3 ,

1 . .

06:37:34 02-06-85 ELECTRICAL MAINTDWCE PEBmt.Y REPORT FW JAMJARYB5 PACE 2 . *l DATE.... GNp00ENT. . . . . FAIL 1RE DESGIPTIN...... CA(SE OF FAIL 1RE. . . . . . . . . CORRECTIVE ACTION........ FR.NO..

BREANER #17 (M 120 VITAL i DETRLNENT PGER BOARD I 1-II, TAPE LEADS (F EACN -

WIRE i 01-03-95 2-XA-55 LIFT WIRE 2rfP1 (M BREANER NO FAILURE LIFTED AND TAPED WIRES A031297

1. 17 VITAL DETRtRENT Ale LEADS AS REGLESTED POLER BOARD 2-III LIFT WIRE 2M98 (M BREANER N17 VITAL INSTRLRENT poler BOARD 2-IV, TAPE LEADS OF i EACN WIRE

, 01-03-95 04.0CL-313-061 DEFECTIVE PYRONTRONICS (M DEFECTIVE PYRWTR(MICS REPLACED PYRONTRONICS, A005213 9 20DE 2 CAUBING TROLBLE CLEARED TROLBLE ALARM, ALARM RAN SI 234.6 01-0lH15 1-CW-302 CODEULET C0YER MISSING ON NO FAILURE PUT 3" COWLA.ET COUER (M A244423 CopWUIT PDETRATION MC ColGUIT PDETRATION MC u 3555 3555 01-03-95 2-FCV-001-0004 WIRES BEIIG SIERTED ON NO FAILURE PLLLED WIRE OUT, PLLLED A237427 l CGTEM LAERE WIRES CODE BACK IN AfD RE-TERMINATED INTO 2-FCV-1-29 ADO ALSO Ale SEALED C00eUIT. WIRE 2-FCV-1-4 WAS PULLED OUT SY MISTANE. CLEADED 40 4

LLERICATED LIMIT SWITDES i

j j 01-0lHI5 N S-003-0175- AUXILIARY FEEDWATER NAfD SWITCN BR(MEN REPLACED NAle SWITCN AS A297439 i A ISOLATI M VALVE IN REGLESTED

! C(MTROL R0lN1 WILL leT '

i \

WMK s 01-0lH15 2'-FCV-077-0415 PLLL CABLE 2VB914 FROM NO FAILURE PULLED CABLE 2V8914 FROM A299852 PADEL 0-L-2 SAB LDE PDETRATION #36 AleWLS 10 1

i l i

I

~

06:37:34 O M 6-85 ELECTRICAL MAINTEMAfCE lEBmt.Y REP (RT FOR JAfRIARY95 PAGE 3 .

i DATE.... (Ill900ENT. . . . . FAILLRE DES (RIPTI(M...... CAUSE OF FAIL 1RE. . . . . . . . . CORRECTIVE ACTION........ fR.lG..

EIN.669 TO PEETRATION (H.-2 LIGUID PAfE1. ELY .

l- 1836, AZDtJTH 151 DEGREES 669 SPLICED PER IRA 29EFE5 i ELV 693 PER M8AI 7-BREEDED PEETRATION PGt TI 77 AfD MSAI 13 01-03-85 0-GENB-082-002 RENWE Ate IIGFECT TE le FAILURE INSPECTED GOVERNOR Ale A297889

~

D-B ELECTRIC GOWERfER CorpLETED MI 4.20 AS CEBGECTtR (M TE ACTUAT(R REGLESTED OF ENGIE 231 ABC

, REll6 TALL BEFORE RLBB4IDE TE temt.Y PDtFORfWEE .

OF SI 7 DATD IS EEDED FtR PRO 1-64-414

! 01-04-85 2-FCO-3H295 FCO-30-295 LEEDS TO Bd le FAILURE PLACED .AfpER ON 641 A120590 I

.AFFED GPEN 90 THAT IIRMINALl? 11 Af612 AfC 2-31C-1782 CAN BE RETLRED TO ICRMAL PER fE INSPECTED PER SI 233 6.20

g

'C1-04-95 1-FCO-030-0295 FCO-30-295 DEEDS TO BE NO FAILURE PLACED JUrpER ON TB 641 A120589

.ANPED GPElf SO THAT TERMINALS 11 AfD 12 AfD 1-31C-1707 CAN BE RETURED TO NORMAL PER fE l: INSPECTED PER SI 233 4.20 l 01-0 N I5 1-OGB-250-4J- BATTERY DISCHARGE OR ArtETER RELAY 104 REPL. ACED ArtETER RELAY A301221 i G CHARGER FAILLRE ALARM IN DEFECTIVE l

. M IT SMOLLD NDT BE 01-04475 NRCK-234-054 SLPPLY LIE TO BORIC ACID BLOUN FUSE (M SAFETY LIE REMOVED CONTROLLER Ale A301077 P BLDGER IS COLD TO BORIC ACID BLD OER REPLACE 0 FUSE CHECNED CIRCUIT FOR CONTDEJITY CIRCUIT READ 35 0195 CIRCUIT DRAMING 6 AMPS AFTER FUSE CHAICE

! TEFFERTLRE RISING 1

.i

! s l .

0 i .

l 06:37:34 0 H 6-85 ELEETRICAL MAINTENANCE temLY REP (RT F(R JAfRIARYB5 PAGE 4 ,

DATE.... (Irp0 DENT. . . . . FAILL5tE DESOtIPTION...... CAUSE OF FAILIAtE. . . . . . . . . CORRECTIVE ACTION........ IR.DC..

J i

DEGREE PER MIMJTE -

1 01-04-95 2-HTCM-234-005 EAT TRACE CIRCUIT 54 BAD T)ERPEBt C(BITitG.1.ER REPLACED TtERfD4 '

A301080 4 NOT OPDIATDE PROPERLY CONTROLLER -

s

} 01-ONIS 2-SCTA-963-001 SAFETY INICTI(M l(RY D(M BAD RELAY REPLACED l(RY DON RELAY A085220 H RELAY WILL DET CHANGE STATE WITH Il9UT CHAICE 01-09-85 2-FCV-063-0023 SAFETY IHKCTI(M SOLENDID COIL BURDED LP REPLACED BAD COIL A30'162 ISOLATION VALVE WILL NOT DOES NOT LET SOLENDID OPEN LSEN Hefe SWITCH IS DERCIZE (PERATED -

! 01-09-G5 14003-0156A SELDOID TO VALVE . BAD CONTACTS G4 SWIltH REPLACE 0 SWITCH UITH IEN A302063 MtBLLATGt IS REMAINING PLUG TYPE SWITCH ADJLETED DetGIZED WFEN IT LIMIT SWITCH SGA.DNIT BE

" 01-09-85 0-LOCOL-013-06 20DE 317 TRotBLE LIGHT TRolBLE LIGHT WI 24-30 REPLACED 2A-30 CARD A085215 G5 EDMITTING DIAL CARD WAS BAD ,

TROLBLE LIGHT ON 24-30 CARD WAS BLNtNT OUT I SYSTEtiS WAS WWtMDE PROPERLY BUT COULD NOT GET TROLBLE IleICATION i WITH TROUBLE LIGHT OUT FUNICATELY DECMED NO ,

1 TDtMINATIONS MADE 01-10-95 1-RLY-030 REPLACE AGASTAT f10 DEL NO FAILURE REPLACED AGASTAT AS A249344 7012PH TItet (3111N. TO REelESTED. VEltIFIED 30 MIN. RANGE) WITH AN CONTACT rinet AFTElt TIfE

AGASTAT litBEL 7012PF DELAY OF 10 MIN 27 SEC BY

! TIFElt (1 MIN. TO 10 MIN. JUIPING OUT TE PHASE B ,

RANGE) REFDtENCE PRO ISOLATION SIGNAL. ND

, 1-94-440 DOCUfENT ON TACF TERMINATIONS FIADE i

f l .

j 06:W:34 O N M-85 B.ECTRICAL MAINTENADEE FDmLY REPGtT FIEt JAlWARY85 PAGE 5 .

l DATE.... (IRP00ENT. . . . . FAILURE DESCRIPTION...... CAUSE OF FAILLstE. . . . . . . . . CORRECTIVE ACTIOK....... Pet.le. . -

i 16 1-84-124-30 -

) 01-10-85 2-RLY-030 REPLACE AGASTAT MODEL le FAILURE ~ REPLACED AGASTAT AS A249345 i 7012PN TIFElt (3 MIN. TO REGLESTED UERIFIED -

j- 30 MIK RAN E)UITN AN CONTACT CLOSES AFTER TIM i

AGASTAT FMEEL 7012PF DELAY OF 10 MI& 27 SEE.

T,IrER (1 MIN. TO 10 MIK \

BY JLFFI6C OUT TtE PNAK

! RANGE) REFEltENCE PRO 8 ISOLATION SIGNAL. MD 1-84-440 DOCUPENT ON TACF TERMINATI0l# MADE HD 1-84-124-30

01-1E NtLY-030 -

REPLACE AGASTAT F10 DEL ND FAILURE REPLACED AGASTATY AS A249343 .

j 7012PN TIPER (3 ftIN. TO REGUESTED VEltIFIED -

30 FIIK RANGE)MITN AN CONTACT r's ret AFTER TIfE AGASTAT FIODEL 7012PF , DELAY OF 10 MIR 27 SEC.

TIrER (1 FII& TO 10 FIIN. BY JR9ING OUT TFE PHASE RA6EE) REFEltDEE PRO B ISOLATION SIGNAL. Se

, 1-84-440 DOCIRENT ON TACF TERMINATIONS rlADE HD 1-84-124-30 l..

01-10-85 NtLY-030 REPLACE AGASTAT F10 DEL NO FAILURE REPLACED AGASTAT AS A249346 '

7012PN TIfER (3 ftIN.TO 30 REelESTED YElt!FIED FlIN. RANGE) UITN AN CONTACT CLOSES AFTER TIRE l AGASTAT fl0 DEL 7012PF DELAY OF 10 MIN. 27 SEC.

TIrElf (1 MIN. TO 10 f1IN. 8Y Jul9ING OUT TFE PNAGE RAIGE) REFEltOCE PRO 8 ISOLATION SIGNAL. le 1-84-440 DoctFENT ON TACF TERftINATICIS FIADE ,

ND 1-84-124-30 01-14-95 NtS-003-0156A HAVE CONTIFRJITY T)ft0UGN C(34 TACTS RErlAINING CLOSED REPLACED OPEN AND CLO6E A299398 OPEN CONTACTS ON LOOP R"2 ALL TIRES SUITCN, ADJUSTED LIf1IT

STEAM GDERATOR LEVEL SUITCN F0lt PROPER LIGHT CG4TINL UALVE OPERATIONS 01-14-65 NtLY-082-fftX2 DIESEL GDEltATOR RELAY NO FAILURE REPLACED PINS IN HINGEB A296556 i 8 f5tX2B HAS BRONEN COVER. ON OLD COVER AfG E

O S

06:37:34 O M 6-85 ELECTRICM. ftAINTENAlCE PE8mt.Y REPMT FM JHJARYis5 PAGE 4 ,

DATE.... GR900ENT. . . . . FAILME DESCRIPTION...... CAUSE OF fan tw. . . . . . . . . CORRECTIVE ACTION........ fR.le.. -

1 4 PIls ARE ff!SSIlC. FRJST REPLACED. NO IEW C0YER ,

HAYE FELL DUT lAEN COVER -

WAS REISYED f 01-14-85 2-FCV-003-0047 WIRES lERE LOGIE POSSIBLE WIRES WERE LOGIE TIGHTDED LOOSE A280179 i DLE TO PRE-W TESTIlG (R C0tGECTIONS DECIED FtR j '

TROUBLE SN00TIls ON BURIED WIRES. HAD PREVIOUS FEtS OPERATIONS DECK FIR PRWElt G8ERATIG4S Ale .

RLH SI 166.6 ALL WIRES l (Di REVERSING CONTROLS WAS TIGNTEN. WIRES WERE NOT BURIED OR COLGtED le TERl11 NATIONS IEltE f1ADE i'

01-14-115 0-HTCK-234-010 EAT TRACE TD BORIC ACID BAD lEAT TRACE CIRCUIT WORKDE PROPERLY A284474 APSS TADBC "B" SAM LE-MALVE AT THIS TIfE WAS WORIED 2-62-1054 WILL IST EAT DN PREVIOUS ist G

01-14-85 2-IGN-268 SEVERAL IGNITERS WOULD BAD CAPACITOR REPLACED CAPACITOR A298412 HDT IGNITE

! 01-17-85 0-XFD-311-0230 OtE HALF OF XFD 230 IS BAD FUSE LIl4( REPLACED FUSE Lite ( A122472 CLOSED Ale IEEDS TO BE RE SET

. 01-17-115 0-XFD-313-0908 FIRE DAf58ER IS IN A BAD FUSE LIl4C REPLACED FUSE LItG( A122483 TRIPPED POSITION Ale EEDS TO BE RESET ,

.i 01-17-85 0-XFD-311-0233 DAfFGt APPEARS TD BE BAD FUSE LIle( REPLACED FUSE Lite ( A296557 rs turn 01-17-85 0-XFD-311-0214 XFD-311-216 WAS FOUND IN 8AD FUSE LIle( REPLACED FUSE Lith ( A122466

! TtE TRIPPED ColeITION Ale

EEDS TO BE RESET J

l '

l .

l -

06:37:34 02-06-85 E.ECTitICAL flAINTENANCE FOfTM.Y REPGtT FOR JAMIARYIH PAGE 7 ,

5 DATE.... (IlWOENT. . . . . FAILURE DESCRIPTION...... CAUSE OF FAILL5tE. . . . . . . . . CORRECTIVE ACTION........ f5t.DC. .

l

~ 01-17-95 0-XFD-313-0906 TE "S" lEONS MO NO BAD FUSE LIE 114INTAEE REPLACED "S" A122490 FUSEIBLE LIE ON TE FIRE N00NS, ELECTRICIAfB DAMER EED TO BE REPLACED FUSE LI M

, REPLACED 01-17-95 0-XFD-311-0224 DAMER WAS FDLAG IN BAD FUSE LIE REPLACED FUSE LI E A122461 TRIPPED POSITISI Ale EEDS TO BE RESET j

01-17-95 0-XFD-311-0233 FIRE DAMER IS IN TRIPPED BAD FUSE LIM REPLACED FUSE LIM A122M3

{

POSITION Ale EEDS TO BE RESEr O'-17-95 1 0-XFD-311-0217 XFD-311-217 UAS F0l20,1N BAD FUSE LI* REPLACED FUSE LIle( A122M1 TE TRIPPED CGOITION AfG EEDS TO BE RESET .

J 01-17-95 2-Clet-313 110 TOR BEARIlGS ICISY, FIAY NO FAILURE tt0 TOR BEARIlGS OK A302049 y IED GREASDC READJJSTED MAD PRESSLRE 01-21-25 2fSV-062-0074 FUSES NEEP BLOWING IN T E BAD MAND SWITCH DID NOT HAVE NAND SWITCH A049399 VALVES CIRCUIT A-8 0F TE IN STOCK CLEAE D CONTAC1S

] CVCS ORFICE LET DOL 41 PUT OLD DE BACK IN IN VALVE ON UNIT 2 CONTROL OR00t TO BRING UNIT LN8 R00rl PAEL 2-ft-6 REPLACED Male SUITCH ON ANOTER f5tA249350 01-22-95 0-XFD-311-0222 SLRNABLE LIE BAD WILL BAD BURNABLE LIle( REPLACED BURNABLE LI M A288580 NOT LET SFIONE DA M ER OPEN IN FECHANICAL EGUIPtENT R00rl 01-23-95 2-ffTR A-074-001 2A Rift PLRP F10 TOR UPPER NO FAILURE ADDED 8 OZ STO 2 OIL TO A300154 04 BEARING EED6 OIL ADDED TOP M O 8 OZ TO BOTTort BEARING OF 2A RNR PUl9 i

i .

I J . i

.?

l 06:37:34 ON M-85 ELECTRICAL t14INTEMMCE POmt.Y REPGli FtR JA142RY85 PAGE 8 ,

DATE.... (IB90 DENT. . . . . FAILINE DESCRIPTION...... CAUSE OF FAILtRE. . . . . . . . . - CORRECTIVE ACTION........ PR.lG.. -

t 110 TOR ,

01-23-95 2-HS-062-40744 REGEM RATOR E AT DArl4GED C(MTACT BLOOC REPLACED CONTACT BLOCK 04 A249350

-A EXCHAfEER LET DOLM Male SWITCH s ISOLATION VALVE C WILL NOT WORK 01-23-85 0-SCTB-032-002 "A" AIR CG9RES80R WILL TRIP COIL SLftNT GUT REPLACED TRIP COIL A300152 1 5 NOT RLM 1-8-85. Fl! 6.20 WAS UBED FOR WIRE LIFT. NO SPLICEB OR LUGS LERE flADE

}

01-24-85 0-XFD-311-0223 S110NE DAtlpER WILL NOT BLRNASLE LIl4C BAD REPLACED BURNASLE Lite ( B4 A302854 (PEN PREVENTIls AIR DUCT EXCHAICE IN PECHANICAL, EeUIPIENT ROOrt 01-25-85 2-IGN-268 LMIT 2 H2 IGNITER BAD IGNITERS REPLACED 60 WIIM S/N692 A121941 CIRCUITS 1A Ape 68 FAILED APO 1A WITH S/N 693 g SI 305.2 REPLACED 2 IGNITERS AS REelESTED 01-25-85 0-8ATO-250-eY CLEAM OXIDATION FR0ft le FAILURE PREVENTIVE CIEAIED Ale DECNED VITill A297848 BATTERY POSTS AS REGUIRED 114INTANCE BATTERY IV PER flI 10.32 DN 125 VOLT D.C. VITAL l BATTERY IV

'l 01-25-65 0-BATB-082-C-S SPARE DIESEL GEE RATOR NO FAILURE ADJUSTED CHARGER Als A242440 i BATTERY WILL PCT ADJUST CALIBRATE 0 FETER. FLOAT BELOW 154.2 VtLTS (M 143.2 EGUALIZER 153.8 EeUALIZER CHARGE CSSC FETER 8521936 DLE 3-25-85 01-29-85 2-BlGtC-099-032 REACTOR TRIP BREANER "A" NO FAILURE ELECTRICIANS PERFORtlED FIE A300157

0 FAILED TO OPEN l&EH LO LO 10.9 PERFORfED FI 19 8 STEArt GOERATOR LEVEL SI 227.1 DROP OUT YOLTAIE a

e

06:37:34 02-06-85 ELECTRICAL HAINTDWCE FDmLY REPORT Fat JMOWtVII5 PAGE 9 .

DATE.... GlrP00ENT. . . . . FAIL 1RE DESCRIPTION...... CAUSE OF FAILIRE......... CORRECTIVE ACTION........ PUt.ND.. -

TRIP SIGNM. WAS DECNED DROPPED OUT INITIATED. WOLLD TRIP APPROX 19 VOLTS.

LAEM OPERATED FR0rt HMS ,

I SWITCH RT-1 51 records listed. .

1 t

t 9

b t

9 i

, I t

SUMMARY

OF WORK COMPLETED

ELECTRICAL MODIFICATIONS SECTION JANUARY 1985 DCR 1739 - VAACS Panel wiring continued during this period.

ECN 5194 - Iodine Monitors Work remaining consists of installation of door locks and new door frames.

Security wiring is in hold until another ECN is executed.

ECN 5198 - Technical Support Center Changes to the annunciator system are in process.

ECN 5202 - Fifth Diesel Generator Cable pulls and splices are in process.

ECN 5712 - Evacuation Alarms Major cable pulls in the auxiliary building are in process.

ECN 6018 - Installation of Space Heaters, Auxiliary Feedwater Pump Motors Unit I conduit is being installed.

ECN 6055 - Fourth Wide-Range Pressure Transmitter i

All nonoutage work is complete.

Appendix R i

Work continues on the first five interactions. An. implementation schedule has been developed.

4 9

23

,, ._ _ . - . ._.._m. .,, -.- .- ,

i Instrument Maintenance Monthly Report l l

January 1985 l

l 1

Unit 1 l

1. Pressurizer level channels L-68-320, -335, and -339 have been operating within the five percent channel deviation as required. All channels l have been in service all month.

2. During the monthly calibration of the UNI level switches all switches I were found within technical specification tolerance.

3. Supported CDWE cleanup and replacement of the density element due

-to solidification.

4.

The P-250 process computer was declared inoperable twenty times during j the month. The computer was restarted and returned to service without appreciable down time. The P-250 will be removed from service and cleaned during the next unit outage of sufficient duration.

5. NCR SQN-NEB 8407 was issued on 12/6/84 to report possible mislocation of Class IE equipment. Radiation detectors RE-90-275 and -276 were specified in the instrument tabs as monitoring the reactor coolant  ;

drain tank discharge lines and RE-90-277 and -278 were specified as monitoring the reactor building sump discharge lines. Visual in-j spection and testing on 11/20/84 revealed that the monitoring de-l tectors were functionally reversed. The problem was corrected by

' TACF 1-84-123-90 on 12/7/84. FCR 3110 was written to revise the drawings.

Unit 2

1. During the monthly calibration _of the uni level switches all switches were found within technical specification tolerances.

2. NCR SQN-NEB 8407 was issued on 12/6/84 to report possible mislocation of Class IE equipment. Radiation detectors RE-90-275 and -276 were specified in the instrument tabs as monitoring the reactor coolant drain tank discharge lines and RE-90-277 and -278 were specified as I

monitoring the reactor building sump discharge lines. Visual in-4 spection and testing on 11/20/84 revealed that the monitoring de-i tectors were functionally reversed. The problem was corrected by '

TACF 2-84-122-90 on 12/7/84. FCR 3110 was written to revise the drawings. l

3. During startup from the outage'6 RPI connectors failed. Causes -

were determined to be open wires in the connectors and water in the connectors. Seven rod control connectors also failed due to wiring '

problems at the connectors. .

4. Other work is shown on the attached list.

I l

24

. -. , - - , . --,--a -

l .-

, INSTRtFENT MAINTENANCE 110NTtR.Y SUrt1ARY 02-05-85 PAGE 1 -

l CO@

f1R.CO@ U FUNC SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . .

A085230 2 FT 063 173A 01/21/85 2-FT-063-173A, LOW INPUT TO CO@ UTER CAUSING OUT CONSTANT EAD ON TE HIGH SIDE OF TE ,

OF RANGE LOW READING FLOW TRANSMITTER HAD LEANED DOW.

RECALIB. FLOW TRANSMITTER ADO REFILLED i LEG ON HI SIDE OF TR#tSMITTER.

A285298 0 077 5007 01/11/85 0--077-5007, REC 0l#ECT DENSITY CELL ELECT. WIRES DENSITY CELL WENT BAD. REPLACED, AFTER PECH. SECTICH INSTALLS IN LIE RECALLED AlO FWCTI0leLLY -

l A286994 2 M1 092 5006M 01/10/85 2-Xn-092-5006K,n00ULE OUTPUT IS ZERO MO HAS BAD IC'S Ale BAD PEN ON 110DULE. REPLACED LODSE PIN ON COPeECTOR. BAD PEN ON 1100ULE AND '

A-10-A-11-A-12-IC'S '

A286996 2 TIS 074 19 01/21/85 2-TIS-074-19, ALARn IS IN AND OUT WITH NO CHANGE BAD TEW SW. REPLACED AlO RECAL SW.

IN TEN A298075 2 FT 003 35A 01/22/85 2-fT-003-35A,PERICDICALLY BLOW DOWN SENSING LOW TErP OUTSIDE. BLEW DOWN SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING A298076 2 FT 003 358 01/22/85 2-fT-003-358, PERIODICALLY BLOW DOWN SENSING LOW TE@. DUTSIDE.

LIES TO PREVENT FREEZING A298077 2 FT 003 4BA 01/22/85 2-fT-003-48A.PERICDICALLY BLOW DOWN SENSING LOW TEM OUTSIDE. BLEW DOWN SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING i y A298078 2 FT 003 488 01/22/95 2-FT-003-40B,PERICDICALLY BLOW DOWN SENSING LOW TEM OUTSIDE. BLEW DOW SENSE LIES c i LIES TO PREVENT FREEZING

' PERIODICALLY TO PREVENT FREEZING A298079 2 FT 003 90A 01/22/85 2-FT-003-90A,PERICDICALLY BLOU DOWN SENSING LOW TE@ OUTSIDE. BLEW DOWN SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PRENENT FREEZING A298080 2 FT 003 908 01/22/85 2-FT-003-90B, PERI (DICALLY BLOW DOWN SENSING LOW TE@ OUTSIDE. BLEW DOWN SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZIE -

l A298081 2 FT 003 103A 01/22/85 2-fT-003-103A, PERIODICALLY BLOW DOWN SENSING LOW TE@ OUTSIDE. BLEW,DOW SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING A298082 2 FT 003 1038 01/22/95 2-FT-003-103B, PERIODICALLY BLOW DOWN SENSING LOW TEnp OUTSIDE. BLSI DOW SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING A298461 2 099 TR-A 01/14/85 2--@79-TR-A, REMOVE SEMI-AUTOMATIC TESTER BOARD TE SEMI-AUT0f14 TIC TESTER CARD NAD A  :

Ale REPLACE SEMI-AUTOMATIC PREMATURE INTEGRATED CIRCUIT CHIP FAILURE. REPLACED TE SEMI-AUTonATIC TESTER CARO.

4 A299566 1 FT 003 103A 01/22/85 1-FT-003-103A, PERIODICALLY BLOW DOWN SENSING LOW TE@ OUTSIDE. BLEW DOWN SENSE LIES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING A299567 1 FT 003 358 01/22/951-fT-003-358,PERICDICALLY BLOLOOWN SENSING LIES LOW TE@ DUTSIDE. BLEW DOWN SENSE LIES TO PREVENT FREEZIls PERIODICALLY TO PREVENT FREEZING A299568 1 FT 003 1038 01/22/85 1-FT-003-103B, PERIODICALLY BLOW DOWN SENSING LOW TE@. DUTSIDE. BLEW DOW SENSE LINES LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZItC A299569 1 FT 003 908 01/22/851-FT-003-908,PERICDICALLY BLOW DOWN SENSING LOW TN OUTSIDE. BLEW DOW SENSE LIES 1 LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZIPE A299570 1 FT 003 408 01/22/951-FT-003-40B, PERI (DICALLY BLOW DOWN SENSING LOW TEM OUTSIDE. BLEW DOW SENSE LIES J

LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZING i

INSTRWENT MAINTENANCE f10 NIM.Y SUrt1ARY 02-05-85 PAGE 2

• CDW '

FWt.C0rp U FUNC SYS ADDRESS. DATE. . . . DESCR IP T I ON. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . . . . . . . . . . . . . . . . . . . . .

4 A300102 2 LEV 003 148 01/14/85 2-LCV-003-148,LCV WILL NOT CLOSE C0rPLETELY MILLIVOLT TO CIAtRENT BOARD ON TE STEAM ,

GEN. #3 LVL MtBIFIDt NAD A SAD

CAPACITOR. REPLACED M CABACITER IN TE FEDIFIER AfC VERIFIED PRWER OPERATION A300194 2 FI 003 103A 01/20/85 2-FI-003-103A,I!OICATOR FAILED MI - REPAIR WTR IN SENSE LIES. E.ED UTR OUT (F '

t SENSE LIES -

A300197 0 TI 068 31fi 01/25/85 0-TI-068-318,TErp IlOICATOR IS READING 600 DEG THE TES. FEDIFIER Uf6 OUT OF CALIO.

~

t F. IMICH IS 200EG ) PRZ TEM AS INDICATED BY MIGN. RECALIS. TE TB9. FEDIFIER 2-TI-68-319 .,

! A300245 2 085 01/11/95 2--085 , ROD D4 TE F250 COMUTER IS PRINTIls EIT VOLTAGE LOW ON D4 SIAIPLY. ADJUSTED D4 ROD POSITION DEVICTED 12 STEPS FRon BAfGC VOLTN;E ON D4 SUPPLY A300312 2 LI 068 339 01/14/85 2-LI-068-339,LVL INDICATOR NAS 6% DEVIATION. REACTOR COOLANT SYSTBt LEVEL TRANWIITTDt i

INSPECT / REPAIR WAS OUT OF CALI8. RECALI8. TK LYL l TRANSMITTEit TO TE VLYS SPECIFIED (M TEPPORARY CNAIEE R85-WM1, BACNFILLED, ADO RETLRfED TO SERVEE.

u A'00806 3 2 099 SPARE 01/15/85 2-099-SPARE,DETERMIE BAD CorFGENTS Ale REPAIR A BAD TRANSISTOR ON M IAGOt VOLTAGE

• BOARD LENT SAD. REPARED TE LAEER YOLTAGE 80ARD BY REPLACDC A BAD TRANSISTOR. _

A302092 1 FT 003 484 01/22/851-FT-003-40A, PERI (DICALLY BLOW DOWN SENSDC LOW TES. OUTSIDE. BLEU Dolm SENSE LIES LIES TO PREVENT FROM FREEZING PERIODICALLY TO PREVENT FREEZING A302093 1 FT 003 90A 01/22/951-fT-003-904.PERItBICALLY BLOU DOWN SENSDC LOW TES OUTSIDE. BL5l 00L91 SENSE LIES .

LIES TO PREVENT FREEZING PERIODICALLY TO PREVENT FREEZDC A302690 2 LI 068 339A 01/14/85 2-LI-068-339A, uIu VERIFY PROPER CALI8. OF NDE. PCE-CAL. TRAN9tITTUt TU LOW De LI-68-339A 0F SCALE A302715 1 LI -063 51 01/22/951-LI-063-51,NIGN LVL INDICATED. SUSPECT FROZE LOW TES. OUTSIDE. SLEW DolM SENSE LIES ,

LIE ALSO XFDtRED TO ELEC TO REPAIR lEAT TRACE A529251 1 PDI 030 133 01/25/85 1-PDI-030-133, min DP PRESS. IS READING 0 TRANSrtITTERS DUT OF 04L. RECAL.

TRANSMITTERS 29 records listed.

4 _ .

INSTRLFENT FIAINTEMAKE f10NT}LY SLFRtARY 02-05-85 PACE 1 Corp

• tm. Corp U FLNC SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTIN. . . .. . . . . . . . . . . . . . . . . . .

A251246 0 PDIS 030 1 6 01/02/85 0-PDIS-030-149,0-PDIS-30-149 IS READIIC -0.3B" 8AD CNTRG.LER. REPLKED CMTRELER H2O DLRING AN 'A' TRAIN ABI SIGNAL A297299 2 FCV 062 139 01/05/95 2-FCV-062-139,VLV. SWINGS FLOW SO BAD'IT STOPS CONTRELER OUT OF ADJSTIENT. FIE Tt9ED T E AUTO f1AKE 17. INVESTIGATE CONTROLLER A300213 2 HIC 062 81A 01/09/95 2-HIC-462-91A, u!N CtMTROLLER IS ERRATIC CAUSIlt IDE. N0ff, PROCESS IS SWIEIDC M FLOW Ale PRESS. TD SWING FLUCTUATING, pc IDET. PRWLEr1 FUL90.

A302706 0 PCV 077 116 01/05/85 0-PCV-077-116,VLV. WILL NOT CMTROL PRESS.

CONTROLLER CUT OF ADJSTFENT. RGRAAST CONTROLLER 4 records listed.

U

~

Mechanical Maintenance Section January 1985 Unit 0

, 1. Cleared blockage in the CDWE heater and the 16" line from the heater to the vapor body.

2. Furmanited various secondary side leaks on both units, especially the eroded extraction and operating vent lines going to the condenser.

3. Replaced the broken crankshaft in the "B" Auxiliary Air Compression.

4. Supported freeze protecton and thawing of the feedwater sense lines.

5. Repaired the traveling water screens that were frozen causing low CCW flow.

6. Repaired fire stops and penetrations found during the performance of SI-233.

7. Inspected the Diesel Generator Buildings.

Unit 1

1. Plugged a leaking tube in 1B2 condenser waterbox.

Unit 2

1. Repaired the #3 Heater drain tank level control valves, 2-LCV-6-106A and 2-LCV-6-106B.

2. Repaired broken hangers on the Unit 2 steam generator blowdown lines in the Turbine Building.

3. Repaired leaks on the Unit 2 hydrogen side seal oil heat exchanger.

Common

1. The diesel generators were inspected per SI-106.

28

o J

Mechanical Modification Section January 1985 ECN 2768 - REVLIS PMTs were completed with no problems. Work documentation was completed.

Work began on the preparation of work for the " improvements" for unit 1.

This includes modifying the seal table tie-in and the unit 1 vessel head attachment.

ECN 5773, 6196, 5856 Pressurizer Work Due to leakage.during start-up, the loop-seal drain valves were closed. An 1

additional hanger was modified.

ECN 2780 5200 - PASF PNTs were completed. Painting is underway. Workplans were prepared for several discrepancies for unit 1.

ECN 5842.- Cavitating Venturi PMTs were completed. Some additional hanger work is anticipated.

ECN 5938 - FW Heater Replacement Work was started on the relocation of ductwork, building structural mod-ifications, the piping modifications, and the modification of the Hartsville Heater Nozzles.

• ECN 6362 (

Additional supports for the ERCW to the diesel generators were installed.

I ECN 6302 Additional support was provided to Auxiliary Building block wall to qualify

.the wall for a siessic event.

ECN 6289 Work was started to replace the concrete blow-out panels for the valve rooms. Two plugs were poured but not installed. Approximately 14 panels are to be replaced.

" Appendix R" - Initial walkdowns of the sprinkler . location was completed.

~

Schedules were developed for implementation. EN DES in working'on the preparation of ECNs and purchasing materials. Field work is scheduled to begin on these items April 1, 1985. Additional walkdowns are scheduled to start on Januity 7, 1985.

l l

29

P

SUMMARY

OF WORK COMPLETED MECHANICAL MODIFICATIONS SECTION JANUARY 1985 2780 - PASF 5200 - Painting and drainage work continues.

-5938 - Feedwater Heater Replacement The duct that has been rerouted between the unit I and unit 2 turbines. Three of the unit l 'and unit 2 turbines. Three of the six #4 heaters have had their nozzles replaced (x-raying is still required). Piping reroutes. work has begun in both the shop and field. Lube oil and instrumentation reroutes were completed.

the installation of the monorail continues.

Appendix R The walkdown of the control building fire protection was completed. Work estimates and planning activities continues.

The first mechanical ECN's are anticipated in February.

5878 CDWE Modifications 5990 Pre-outage work continues.

5373 - Con-Demin Air Comprassor Work continued on the raw cooling water air tie-ins.

I NUREG 0588 5895 - All 11 non-outage solenoids have.been replaced. Seventeen outage required solenoids will be replaced during the ice weighing outage in April.

6328 - Two additional solenoids were replaced.

6200 - Relocation of the Main Steam Pressure Transmitter Alinon-outageworkwascompleted. The remaning work will be completed during the outage in April.

6231 - Pipe reroutes

- The workplan is being prepared to reroute the piping to allow l for the installation of the new motor operators. I j 30 i _

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

r;

. :o

.a TENNESSEE _ VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 February 15, 1985 Nuclear Regulatory Commission

. Office of Management Information and Program Control

' Washington, DC .20555 Gentlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - JANUARY 1985 Enclosed is the January 1985 Monthly-Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY eP.

lhhY R. Wallaet 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 tp.shington, 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 (1 copy)

Nuclear Regulatory Comission 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)

-' 1983--TVA.50TH ANNIVERSARY An Equal Opportunity Employer