ML20129J565

Monthly Operating Repts for Mar 1985

ML20129J565
Person / Time
Site:	Sequoyah
Issue date:	03/31/1985
From:	Dupree D, Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506100126
Download: ML20129J565 (33)

Text

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.. J-TENNESS$E VALLEY AUTHORITY ' ' ' ' . ~ . -

DIVISION OF NUCLEAR POWER --

~

g SEQUOYAH NUCLEAR PLANT -

__c MONTHLY OPERATING REPORT TO THE _

NUCLEAR REGULATORY COMMISSION March 1, 1985 - March 31, 1985

..~:- .

UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77

, UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by: - --

P. R. Wallace, Plant Manager ~

8506100126'850 g -O ,,,7 M 94(Q p, e n-

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3. e-C t T5BLE OF CONTENTS

-I. Operational Summary Page LPerformance Summary 1-Significant Operational Events 1-2 Fuel Performance and Spent Fuel Storage Capabilities 2 PORCs.and Safety Valves Summary 2 Licensee Events, Special Reports and 2-3 Diesel Generator Failure Reports 3

Offsite Dose Calculation Manual Changes 3 II. Operating Statistics-A. NRC Reports Operating Data Reports '4-5 Unit Shutdowns and Power Reductons 6-7

~ Average Daily Unit Power Level 8-9 B. TVA Reports Nuclear Plant Operating ' Statistics 10 Unit Outage and Availability 11-12 Reactor Histograms 13-16 III. Maintenance Summary Construction Activities 17 Electrical Maintenance 18-22 Electrical Modifications 23-25 Instrument Maintenance 26-27 Mechanical. Maintenance 28' Mechanical Modifications 29 L ts

7-5 '

Oparntions Summary March 1985 The following summary describes the significant operational activities for the month of March. In support of this summary, a chronological -

log of significant events is included in this report.

Unit 1 Unit I was critical for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 878,860 MWH (gross), resulting in an average hourly gross load of 1,181,263 kW during the month. There are 86.3 full power days estimated remaining until the end of cycle 3 fuel.

The capacity factor for the month was 99.9 percent. The cycle 3 refueling outage is scheduled to start on September 6, 1985.

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

Unit 2 Unit 2 was critical for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 872,320 MWH (gross), resulting in an average hourly gross load of 1,172,473 kW during the month. There are 281.4 full power days estimated remaining until the end of cycle 3 fuel.

The capacity factor for the month was 99.1 percent. With a capacity factor of 85 percent, the target EOC exposure would be reached February 26, 1986.

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

Significant Operational Events EE.it 1 Date Time Event 03/01/85 0001 The reactor was in mode 1 at 100% power producing 1190 MWE.

03/31/85 2359 The reactor was in mode 1 at 100% power producing 1180 MWE. The unit has been in continous operation since September 28, 1984 (184 days).

The units 878,860 MWE (gross) and 99.9%

capacity factor is a record for the unit.

Unit 2 03/01/85 0001 The reactor was in mode 1 at 100% power producing 1190 MWE.

03/31/85 2359 The reactor was in mode 1 at 100% power producing 1180 MWE. The unit has been in continous operation since February 17, 1985 (42 days). -

1

.;c .

Significant Operational Events'

.(Continued)

. Spent Fuel Pit Storage' Capabilities 4 Sequoyah hasi t he capabilities'to store'1,386 spent fuel assemblies.

Two-hundred-seventy-six assemblies _are presently stored in the SFP'

- withL the capacity to store an additional 1,110 assemblies.

/

.PORVs and Safety Valves Summary No PORVs'nor safety valves were challenged during the month.

Licensee Events-and Special Reports

-The following. licensee event reports (LER) were sent during March 1985 Lto .the Nuclear Regulatory Commission.

LER DESCRIPTION OF EVENT 11-85011 On seven separate occasions, an hourly fire watch was not performed within one hour. All events occurred while.both units were in mode I at 100% power.

.The events were: '

, Time (CST) Date Location /Cause

-2200 February 6, 1985 LERCW Pumping' Station.

~

Keycard control for' door PS-4 would not function.

0400- February 8, 1985 ERCW Pumping Station. Keycard control for door PS-6 was

.. frozen.

0215 Februa ry 12, 1985 ERCW Pumping station. -Door PS-5 was frozen shut.

1016 February 12, 1985. ERCW pumping station. A new power block security gate blew shut and locked.

1200 -February 13, 1985 ERCW pumping station. Door PS-5 was jammed and could not be opened.

'0832. February 15, 1985 Auxiliary Building. Door A183 would not open due to a bad relay and cardreader.

1427 February 28, 1985 TSC. The access door to the TSC will be a keycard door under powerblock. After power _

supply switching, the computer ~

was reprogrammed but control of this door was not defeated as required.

2 L__--_-_____--_-_--_-____-___-____-___-__-________-____-_-_-______.

r -

. a- '*-

t .Licantee Events and'Special Reports (Continurd) 85004 At 1511C on February:_15,i1985 with unit 2 in mode _1 at 100% Power, power.was-lost:to protection set I instrumentation. This caused a-reduction in feedwater flow to all steam generators'and loops _one.

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=

and threeLfeedwater regulator valves to fail closed. The reactor tripped on a lo-lo! steam generator level in loop one. The event-was primarily caused by. personnel error in.that the ASE failed to clearly understand the procedure for removing an inverter from service before

. proceeding.

At 0243C.on February 17, -~ 1985 , - a second reactor trip; occurred due~to

lo-lo level in ! steam generator two. While reducing power because'of an'EHC fluid leak,.the main feed pump tripped because of-low seal-

-injection' pressure _due to condensate feedwater flow fluctuations.

~

2-850'05' With unit 2 in mode '1'at 100% Power at 0118C on: February 12,'1985,

during a' routine inspection of' containment, loose equipment and l-miscellaneous debris was found in the upper compartment.

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

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

l ~

'Offsite Dose Calculation Manual Changes No1 changes were made to the'Sequoyah Offsite' Dose Calculation Manual during the month.

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OPERATING DATA REPORT'

.. +

, e_ DOCKET NO. 50-327 A .DATE. APRIL 4-1985 COMPLETED BY M. G. EDDINGS.

TELEPHONE (615) 970-6421-OPERATIN'GSTATUS ~

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

2.' REPORT PERIOD: MARCH 1985 3.LLICENSED THERMAL POWER (MUT): 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 18.: IF - CHANGES' OCCUR IN CAPACI TY RATINGS (I FEMS NUMBERS "3.THROUGH.-7)SINCE-LAST REPORT, GIVE REASONS: -=_

---

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

.9.cPOWER LEVELETO WHICH RESTRICTED,IF ANY(NET MWE):--------

---

= ---- _--

~10.-REASONS ~FOR RESTRICTIONS,IF ANY:_ - - - _-

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

=_---- -

q THIS MONTH YR.-TO-DATE. CilMULATIVE ci t. HOURS IN' REPORTING PERIOD 744.00- 2160.00 32881.00

12. NUMBER OF HOURS REACTOREWAS CRITICAL 744.00 2160.00 22807.66

13. REACTOR RESERVE SHUTDOWN HOURS 0.00- 0.00 0.00 14.:.HOURSLGENERATOR ON-LINE 744.00 2160.00 22268.95 115.-UNIT ~ RESERVE: SHUTDOWN HOURS 0.00 0.00 0.00 16.' GROSS THERMAL ENERGY GENERATED (MWH) 2534247.48 7326950.80 72004636.75 17.' GROSS ELECTRICAL ENERGY GEN.-(MWH) 878860.00 2532480.00 24268896.00 18.. NET. ELECTRICAL ENERGY' GENERATED (MWH) 846S76.00 2440988.00 23322618.00 19.LUNIT SERVICE FACTOR 100.00 100.00 67.73 20.-UNIT AVAILABILITY FACTOR 100.00 100.00 67.73 T21.. UNIT CAPACITY FACTOR (USING-MDC: NET) 99.12 98.44 561.79-z22.LUNIT CAPACITY FACTOR (USING DER NET) 99.12 98.44 61.79-2:1.-UNIT' FORCED OUTAGi-RATE O.00 0.00 16.86

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

~ Ice.. Weighing _-i. April.26._lRS.5_ . 2fLM -- - - . - - - _ - - _ - - = _ ___--_---

. . . Cycla 1. Refuel.inghiodificnrinn . .Septemberil9.81. ll. dDYa.-- ___=____ _

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

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

NOTE THATuTHE THE YR.-TO-DATE AND

CUMULATIVE VALUES HAVE DEEN UPDATED.

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-OPERATING' DATA REPORT m x . . -

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= DOCKET-NO.~50-328

'DATE APRIL'5.1985 COMPLETED DY D.'C.DUPREE-TELEPHONE (615)870-6248

, OPERATING STATUS;

>1.; UNIT I NAME:;SEQUOYAH' NUCLEAR-PLANT, UNIT 2 NOTES:

2.1 REPORT PERIOD: MARCH 1985 43.'5 LICENSED; THERMAL POWER (MWT): . . ,

.3411.0 74.gNAMEPLATE' RATING.(GROSS.MWE): ~

. '1220.6 '

35L DESIGN ELECTRICAL; RATING (NET-MWE): 1148.O-J6. MAXIMUM DEPENDABLE: CAPAC11Y . (GROSS MWE):

1183.O' il7.rMAXIMUM DEPENDABLE CAPACITY'(NET:MWE): 1 1.4 8 . 0 18QIFlCHANGESiOCCUR IN' CAPACITY RATINGS (ITEMS: NUMBERS

,' 13'THROUGH 7)SINCE LAST REPORT, GIVE REASONS: . _ .

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

69.. POWER LEVEL TO.WHICH RESTRICTED,IF ANY(NET MWE):= _ - . _ _

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

RIO.JREASONSDFORERESTRICTIONS IF ANY: --

= - - - - - - - - _- _____________________________________

y THIS MONTH YR.-TO-DATE CUMULATIVEl n11. HOURS IN REPORTING PERIOD- 744.00 2160.00 24841.00' D12.' NUMBER:OF: HOURS REACTOR WAS CRITICAL 744.00 2117.70 18812.82 13.OREACTOR' RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 ,

-14L HOURS GENERATOR-ON-LINE~ 1744.00 2085.92- 18356.10 15.~ UNIT RESERVE' SHUTDOWN HOURS. O.00- -O.00 O.00 c 16.' GROSS THERMAL ENERGY GENERATED'(MWH) 2532200.88. 6603664.47 58602675.34~

17.1 GROSS ELECTRICAL ENERGY GEN.- (MWH) 872320.00 2274420.00 19966100.00

18. NETJELECTRICAL-ENERGY GENERATED-(MWH) 842202.00 2189911.00 19210919.60

19. E UNIT - SERVICE FACTOR -

100.~00 .96.57 73.89 120. UNIT AVAILABILITY FACTOR .100.00-- -96.57 =73.89-

21.MUNIT CAPACITY FACTOR (USING1MDC NET). 98.61 8:8.31 67.37 122. UNIT CAPACITY FACTOR (USING DER NET) 98.61 G8.31 67.'37

.23P UNIT FORCED OUTAGE RATE . ~ 0. '00 3.15 '8.00

~24. SHUTDOWNSLSCHEDULED OVER NEXT 6 MONTHS-(TYPE, DATE. AND. DURATION OF EACH):

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---____ = _ -___ ___ =-_=______________

25; IF SHUTDOWN AT~END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

_- _=_.______- = _ _ _ _ _ _ _ _ . _ _ _ _ _ - - ______ _ __

I. N NOTE THAT THE:THE-YR.-TO-DATE AND e CUMULATIVE VALUES HAVE BEEN UPDATED.

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'. l$QNPh 'ATTACl(MENT 1

-AI '

AVERACE DAILY UNIT POWER LEVEL

,Apendix A: .

Pa ge 3 o f 8 Rev. 24' .

FILE PACKAGE NO. 55 DOCKET NO. 50-327 REPORT REQUIREMENTS UNIT. One DATE April 1, 1985' COMPLETED BY M..G. Eddings TELEPHONE (615) 870-6421 .

fl0NTil MARCH Day . AVERAGE DAILY' POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)- ' (?!We-Net)

.I 1151 17 1147

'2. 1151 18- 1143

. 3 1150 -

19 1145 4 1152 -

20 1145

.5 : 1148 -91 11 '+ 2 o

6 1150- 22 1142

'7 1150 23 1140 L8~ --1150 24 1138

'9' 1150. 25 1138

.10 1148- 26 1140

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11 ~ 1148 27 1140 12 1140 -28 -

1140 -

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13 29 1137

_1147

- 14 1146 30 1136 f7 15 1145 31 1142

i6. 1144~

~ :. INSTRUCTIONS 10n this format, list the average daily unit power level in MWe-Net for each day. .--

in:the:repo ting month.' . Compute to the nearest whole megawatt.

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SQNP ATTAClit!ENT I AI-18 .

AVERAGE DAILY UNIT POWER LEVEL Apendix A Page 3 of 8 hev. 24 FILE PACKAGE NO. 55 DOCKET NO. 50-328 REPORT REQUIREt!ENTS UNIT 2 DATE April 5, 1985 COMPLETED BY D. C. Dupree TELEPIIONE (615) 870-6248 fl0NTil MARCll Day AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(?!We-Ne t ) (?!We-Ne t )~

'1- 1143 g7 1136 2 1141 18' 1133 3 1140 g9 1130 4 1142 20 1130 5 1141 21 1130 6 1137 22 1131 7 1131 23 1132 8 1132 24 1134 9 1136 25 1134 10 1131 26 1130 11 1137 27 1127 12 1138 28 1132 13 1138 29 1129 14 . , _

1138 30 1129 15 '1136 3g 1128 16 1137 INSTRUCTIONS On-this format, list tiie average daily innit power level in ?!We-Net for each day .

in the reporting month. Compute to the nearest whole megawatt.

9

• , TVA 7j82A (DNPG 8u NUCLEAR PLANT OPERATING STATISTICS

~

SEQUOYAH NUCLEAR Plant 2

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Period Hours 744 Month MARCil 39 85 7

Item Unit Unit No. Unit No. One Two Plant 1 Aver' ace Hourly Gross Load, kW 1,181,263 1,172,473 1,176,868

. 2 Maximum Hour Net Generation. MWh 1,164 1,148 2,312 i: 3 Core Thermal Eneroy Gen, GWD (t)2 105.5936 105.5084 211.1020 4 Steam Gen. Thermal Energy Gen., GWD (t)2 _105.9634 105.9003 211.863/

8 5 Gross Electrical Gen.. MWh 878,860 872,320 1,/31,IMU j 6 Station Use, MWh 32,284 30,118 62,402 7 Net Electrical Gen., MWh 846.576 842,202 1,688,778

{

0 8 Station Use, Percent 3.67 3.45 3.56 9 Accum. Core Avg. Exposure MWD / Ton! 10,883 3,160 14,043 10 CTEG This Month,10 6 BTU 8.649,387 8,642,402 17,291,789 11 SGTEG This Month 106BTU 8,679.673 8,674,505 17,354,178 12 13 Hours Reactor Was Critical 744.0 744.0 1,488.0 14 Unit Use. Hours-Min. 744:0 744:0 1,488:0 15 Capacity Factor, Percent 99.9 99.1 99.5 2 16 Turbine Avail. Factor Percent 100.0 100.0 100.0 17 Generator Avail. Factor. Percent 100.0 100.0 100.0 0 18 Turbooen. Avail. Factor. Percent 100.0 100.0 100.0 .

$ 19 Reactor Avail. Factor Percent 100.0 100.0 100.0 0 20 Unit Avail. Factor. Percent 100.0 100.0 100.0 2t Turbine Startuos 0 0 0 22 Reactor Cold Startuos 0 0 0 23 Unit Service llours 744.0 g 24 Gross Heat Rate, Blu/kWh 9,840 9,910 9,87d 5 25 Net Heat Rate, Btu /kWh 10,220 10,260 10,24T 3 26 Gross Heat Rate (w/o oil) BTU /lGO . 9,870 0 27 Net Heat Rate (w/o oil) BTU /lGill 10,247 g 28 Thrott!e Pressure, psig 855.6 869.7 862.7

& 29 Throttle Temperature. *F 526.1 527.9 527.0 j 30 Exhaust Pressure, InHg Abs. 2.2 1.9 2.1 E 31 Intake Water Temp., *F 50.3 51.1 50.7 F 32 33 Main Feedwater, M lb/hr 15.0 15.3 15.2 y 34

$ 35 36 37 Full Power Capacity, EFPD 370.00 363.65 733.65 38 Accum. Cycle Full Power Days, EFPD 283.6870 82.2710 365.958C

-M 39 Oil Fired for Generation, Gallons 1,716 2 40 Oil Heatino Value. Btu / Gal. 138,000 41 Diesel Generation. MWh 26 ~

d7 Max. Hour Net Gen. Max. Day Net Gen. Load MWh Time Date MWh Date Factor, %

3 43 2,304 1,900 03/04/85 55,056 03/01/85 98.4 '

$ Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.  !

j 2(t) indicates Thef mal Energy.

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SEQUOYAH NUCLEAR PLANT UNIT ONE i REACTOR llIST0 GRAM f MARCll 1985 -

I-COMMENTS I

The reactor maintained 100 percent power the entire month.

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1 SEQUOYAH NUCLEAR PLANT UNIT TWO

, REACTOR HISTOGRAM MARCl! 1985 C DiENTS

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.g e *:. e MAINTENANCE

SUMMARY

Construction Activities March 1985

ECN L5503, 5111 -Office and Power Stores Facility.

Elev. 710 was transferred.to NUC PR on March 15, with anticipated transfer of Elev.

'694 on April 8. The HVAC system is being balanced at this time. Punch list items and landscaping work remains.

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

~

The project is approximately 80% complete. Work on' Phase I is complete and pre-op-tests are being conducted. A FCR has been written to delete the sewage grinder system and to install a septic tank. It is awaiting approval from design.

ECN 5610 yard piping.isLunderway but cannot be completed until pre-op tests are completed.<

The. turbine building piping and the 4" filtered water continues to be worked. (

L ECN L5841- Hot Machine Shop All. work is complete with the exception of the hallway on Elev. 706. This delay is due to power stores and will be completed when they move to their new facility.

Also a mono-rail is to be added in the De-Con Room.

ECN L5599- Fifth Vital Battery.

This project is complete with the exception of the remaining Appendix R work.

The remaining protective. coating will be applied after maintenance is completed in battery rooms I, II, III, & IV.

.ECN L5202-Fifth Diesel Generator Modification.

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

Pipe installation should be complete by April 8.

-DCR L2108 - Flammable Liquid Storage Building This project is approximately 85% complete. The remaining work consists of:

built-up roof, air conditioning hook-up, testing and clean-up.

ECN L5932-5935 --Power Block Modifications This project is overall 75% complete. Some cable pulling and equipment setting has been accomplished. . Waiting on NRCs approval of the security plan so the g;; remaining work can be completed.

ECN L6342-HP Calibration Facility-The work plan ic being written. Modification work is scheduled to start in April and be completed by the end of May.

ECN L6182' Cooling Tower Repair Cooling towers are in use in their "as is" condition. A requisition is being written'for the repairs.

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'.ILL I:07 CCSECT IC *Fi w.. e,,,....,1 a . i r.

I*-23-35 2-IAT3-H2-00 'I!EEEL 5E:iERATCE 2 M :G :.h0 :i *i ih!S TI.tE CHED.ED FOChD NO GE0bND A335533 0 .; DISTEI?UTION PANEL HAS A AT THIS ::ME ORDUND dEIER 25 M .! FiGATIVE EECUU3 :EADIN3 0 AT THIS i

. .".E (3-25-35 0-EAIB-03:-030 SPMI DIEEEL EE!!ERATOR 90 FAILU:E :FEVE.'!T!VE ALIE3 UATER TO PATTE?.!ES A303234 D4 CATTEEIES L 9 CN UATER m!.NTAiCE AND FUT ON CHARGE ANE CFARGE i

0?-25-d's '-F A H-317  ?!?E TEE IN AD IL!?nt ?t31Y .4: .NEELi FAINTING CLEANEP AND FAINTED ?IFE A290537

i.

!LIINE ELEVA' ION 714 AS REQUEETED IL AtI5 EUSTY OE-2-F; ".-nrRE-)!'.IC

. CHARG:N3 FUM? 2A-A d0iLE EEiEAVCIR leu 0:1 DIL ADLED OIL TO FROFER LEVEL A536660 v OUiiOAE0 IEARIN3 RUNNING H5i 02-U ; 2-iC 1-0 32 'sC0 SIESEL GENERATOR CATER N3 FE0?LEM FOUND HEATERS READING 430 A52i547

'? J/CEET HEATERS 2P-3 EEEF VOLIS FHA 5E TO FHASEr XICf.!hG OUT OFERATG: HAS AhF EEADING A FHA 5E TO EEEET 2 AND 3 ilhE5 A 15.5, B FEAEE 15e15, C EHIFT FHASE 15e5 AND HEATEES ARE CYCLING ON AND OFF AFFFOXMATE*Y EVERY 3 MINUTESe CHED.ED til CONNECTICNSr M0 FRDBLEMS WITH HEATERS AT THIS TIME 1

03-25-95 0-CHGB-250-000 125 VITAL PATTERY CH:F.0ER N3 F/ILLRE UCEK UA3 C0d?LETED ON A517847 J-G STAYS El AND '!ILL NOT .

ANOTHER MR C'm- . t. .,

25-S5 1-C0N-302 CONIUIT CA? E'EVATICN 111 CD!EUIT i.F .1I?3!N3 SEALEP CCNDUIT WITH RTU A244447 (B 01, ABGTS CEILIf3 FOAM APOVE 00CR A183 t

02-23-35 0-CHR-311+15! 'S' C T R3L PUILIING UATER FLO's GUT DF ADJUSTED UATER FL0u A299426

-A CHILLER IS TRIFFED OUT ON APJU3TMENT 9IL FAILLRE 03-25-i5 1-fF9-067-049 CCNTEOL FUEES HAVE NO ALIGNMENT FFCELEM IN C0 ERECTED ALIGNMENT A300340 1 FC%ER FOR 26-A STRAINER CCNTROL CIRCUIT VALVE FRDBLEM LIMITS ON ISOLATION VALVE O

18 i..-........ .. . . .

34 .;

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12:53'45 01 "5 I' : 11TE. .~. . C0aF0 KENT.....

ELECTRICAL MAINTENANCE MONTHLY PEPORT FOR NARCH FAILUVE DESCRIPTION...... CAUSE OF FAILURE......... COREECTIVE ACTION........

PAGE 2 i'R .NO . .

li r-

~

NOT FROFERLY MADE FOR

{/

RELAY FICK UP

>; 03-25-85 I-CHR-311-0028 ELECTRICAL PDARD ROOM WATER FLO'J GUI 0F ADJUSTED UATER FLOW A529597 CHILLER HA3 BUSBLES ADJUSTFENT t 25-35 0-0F03-250 VITAL BATTERY IV VOLTAGE QUT CF ADJUSTMENT ADJUSTED EGUALIZER A302?S4

?

EDUALIZER CHARGER OUT CF V0LTAGE TO 144 VOLTS AT i A0JJ3TMENT FATTERY TERMINiLS l

13-25-85 0-CH2-31?-0!?5 CuILLER LO2 ON F;ECN FLAN 3E LEAKING EEPAIRED LEAKr AND A299402 A

CHARGED UNIT WITH FEEON t.

.03-E-S5 0 CR-313-0303 6.?KV SHUT 00tN 20ARD ENKNOUN AT THI3 TIME CHECKED CHILLER NOTHIN A529529

- 'A ROGM CHILLER A-A FUMFS FOUND URONG TRIP CUT OI-25-65 0-CHOR-250-000 VITAL BATTERY CHAEGER IV EQUALIZER CHARGE UOLTAGE ADJUSTED EQUALIZER A302???

Y-i. WILL NOT CHARGE CUT OF ADJJSTNENT VOLTAGE TO 144 VCLTS 03-25-R 0-dTR3-070 FE; FORM FEEV91TI'E N3 FAILURE ?FEVENTIVE FEFJORdED AI-Is A5 A2S?059 NAINTANCE ON 350 HORSE MAINTANCE RECUESTED f02ER EDTOP SIGRED IN ,

%AREEOUSE

.03-25-55 1-CAIL-093-0FL HIGH RE3ISTANCE IN CABLE NOT KNOUN CUT CAPLE AT FENETRATION A245909 1070 IFL107011066 33 8 RES?LICED CABLE AT FENETRATICN 33 i ~ 03-25 1-GENB-CS2-000 TIME DELAY RELAY FOR TIMER NEEDED RESETTING GESET IIMER PER MR ?FECS A532529 L

15-9 DIESEL GENERATCR 15-B DROPS OUT APPRGX.17 SECOND3 AND SHOULD DROP OUT AT 1010R-1 SEC0NIS 03-25-85 ' 1-HTCK-234-030 ALAiH LICHT IN CIRCUIT HEAT TPACE CAFLE PAD FUT IN NEU Tf?E HEAT A279710 0F 300P UILL NOT RE3ET TRACE AND ADDED T04 5 TO CLEAR LIGHT 03-25-85 1-GENS-032-001 TI.'.E DELAY RELAY 15 TIMER NEEDED RESETTING EESET TIMER AS EEGUESTED A533523 3-B CPERATED AT 105 SECONDS INSTEAD OF 60 EEC.

~ 03-2EE5 iEN-03) PENETRATION 749A12220005 NO FAILURE FREVENTIVE REFLACED SEFA BOARD t.3 A290123 NEED TO REPLACE SEARFORM .NAINTANCE REQUESTED IDARD ON TRAYS h OL-ArEECrGK-A.VAZ 1 FC-4 L 19 LL

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112:52:45l04'-01-3!. ELECTRICV. MINTENAliCE MCNTHLY REPCRT FOR MARCH PAGE 3 CATE.... C0 90 T. . . . .- - FAILi,RE LESCRIFTION...... CAUSE OF FAILURE......... CDEFECTIVE ACTION........ MR.NO..

l 03 M5  !-PEN-020 PENEIRATION 749A5035 M 3 NO FAILURE PREVENTIVE REPLACED SERA E0ARD AS A280186

~

NEED TO REFLEE SEARFJRM MAINTMCE REQUESTED BOARE ON IFAYS HH-b ECVrNI-A 1 VEG 03-25-55 24EN-030 ?ENTPATIO.1 734Al20:0075 NO FAILURE REVENTIVE REPLACED SERA BOARD AS A290166-NEED TO REPLACE SEARFORM MAINTANCE REGUESTED 39ARD ON TRAY llEXT TO TRAY FN-E 430VE 100R v3-25-35 2-IIP. M S-009 125 VITAL BATTERf 13 TFE ALARM SET POINT WAS. REFLACED METER RELAY AND A518262 3 DISCHARGE ALAR!i DID N2T T00 HIGH ADJUSTED TIMER TESTED FOR ALMM GPEN CUEFENT UENT FROFER OFERATIONS AND HIGNER THAN TFE ALARM FETURNED TO SERVICE C3-2^-33' 'ATCE-234-CK3 - HEAT TRACE CIRCUIT 8365 BAD HEAT TEACE SEPLACED HEAT TRACE A291494-

$5 -IS NOT IJORKING CIRCUIT 365 P 3 S d-25-25 2-V! W-250-C10 INVERTER A? NORMAL ALARM FAN :4ILURE MDIGR EAD REPLACED FAN MOTOR A282973 0 CAME IN -

03-25-E5 M HR-?!3-0338 EHUT 00Wh PCwRD RCOM PAD TEMPERTURE CONTROL REPLACED TEMFERTURE A327322

-A CHILLER h-B PEEFS VALVE CONTROL VALVE TRIPPING D'JT 02-2 M 5 2-FS'M47-0339 EMERGANCY GAS TREATMENT BAD ELECTRICAL COILS REPLACED ASCO COIL A528677 5fSTEh ROOM COOLER FAN 102-005-90 WILL NOT RUN 25-85 C-CHGB-250-000 WHEN BATTERY CHARGER IV FLOAT VOLTAGE OUT OF ADJUSTED FLOAT VOLTAGE A528732 J-T ~00ES OFF EGUALIZER ADJUSTMENT CHAR 0ER DROPS TO 90 VOLTS 23-85 0-PAlh-364 FEPAINT FLCCR IN (ENT NO FAILURE PREVENTIVE PAINTED FLOOR AS A253537 FURGE ROOM MAINTANCE REQUESTED 03-25-35 2-INVB-250-000 VITAL INVERTER FAN III BAD FAN MOTOR REPLACED FAN MOTOR A529153 P RUNS INTER.91TTENTLY BEARthG GErilNG HOT

'03-25-85 0-CHGB-250-000 VITAL 1:ATTERY CHARGER RESISTERS BAD K5 ANIR3 REFLACED FESISTERS A298430 H-F flII IS NOT U0RKING ON EDUALI2E

'53-25-35 1-MTRB-003-003- NO CONTROL F0'JER LIGHTS INSTEUMENT LAMPS PAD FEPLACED INSTEEMENT LAnPS A03S538 7-A SHOWING IN nAIN CONTROL PLACED JUMPER ACR0SS 17CR ROOM - TO 17CXI 20

c . - .,

12:53145 04-01-55 ELECTRICAL liAINTENANCE MONTHLY REFORT FOR liARCH FAGE 4

- DATE.... - COM?CHENT.'.... FAILURE IESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION........ MR.NO..

03-25-85 2-FNLA-032-00T DEISEL GINERATO'i GROTiD PAD GEGUND t1ETER REFLACED DEFECTIVE GROUND Ad940?

id METER HDT U0 EKING METER 03-25 0-CH33-250 125 VOLT VITAL PATTERY REEISTER BAD, CAPACITOR REPLACED EESISTER R5, A529174 CHARGER IV WILL NOT HOLD AND ONE DIODE PAD FEFLACED CAPACITOR AND VOLTAGE APOVE 87 VOLTS ONE DIODE e M S-E5 0-L3-082-5015 REE0VE LEVEL EWITCH AND NO FAILURE FFEVENTIVE REMOVED LEVEL SUITCH, A335535 AS5CCIATED JUNCTION FOX MAINTA9CE JUNCTICN P0X AS REQUESTED Af!D CONLUIT TO ASSIST-hECHANTICAL MAINTANCE IN PEFAIR UCRK ON DIECEL CEllEFATOR EFGIKE 1A1

=03-2?-55 I-:-ATB-082-001 - CIESEL del.ERAIDR BATTERY NO FAILUKE PREVENTIVE CLEANED CORFOSION AND A335534 P-t 15-B CELL 12 HAS MAINTANCE AF? LIED NOLAX TO EXCESSIVE CORFCSION ON CONhECTOR COMiECTION TO DISTRISUTION FME'.

CHARGER 07-26 0-MTRS-013-SFA FERFORt B4ILGE AND MEGGER N3 FAILURE PRECENTIVE FEEF0EtiED MI 10.20 AS A518184 RE ' TEST FER MI 10.20 ON NAINTANCE ?EGJESTED.

SP/<RE FIRE FU5F MOTOR 13-24-35 2-HTCT-052-056 CVC HEAT IFACE CIFCUIT HEAT TRACE CAPI.E WAS EEFLACED HEAT TRACE CABLE A282652 5 Es5 HAS SHORT DAMAGED 03-25-35 0-U-0I9 ThE SCLENGID ON TEE HOLD SOLENDID LOO 5E, LAICH GUI CLEAhED AND ADJUSTED A032151 CFEN EEVICES FOR THE FIRE 0F ADJUSTMENT AND DIETY LATCH TIGHTENED SOLENDID D3GR IE CHATTERING TO FEEVENT NOISE RELEASE MECHANISM STILL HEED 3 REFLACING

' 03-26-E5 MTB-250-000 125 VOLT VITAL DIEECT GROUND IS ON 13 STEAM T5 !E COMFLETED Oii A529118 X-7 C!.REENT M ARE III MAS 130 GENERATOR ELOU DOUN- 3R328537 VJLi I,EGATIVE ORCUND IS3LATION VALVE 03-24-85 1-5EhB us2-000 i:IEEEL 3ENERATOR 1A-A DIR!Y PATTERIES CLEANED 1AITERIE3 A:iD A257533 u s- IATTERY HAS A 15 V 1.T RELUCED GROUNL TO 2.5 hEEATIVE B5 01D .D.C

. 73 GROUND 03-2 H 5 0-icL- a H l1 PfR0!RCNICS FANEL 610 UATER IN C0 C JIT CAU5Ih6 EE? LACED DETECTOR CLEANED A52i273 0 IOi2 IIS-B UNIT 2 HEAT CCER055 ION ON IETECTOR iATER TE:st CCEUIT AND VENT FAN HAS Is00E E CCMACTS XS-13-161E L!CHT AND CON'T CLEAR 13-i H 5 2-HTCK-062-004 LVC HEAT TFWiL3 CLEEENT RELAY EAD EEFLACED EELAf USING A297N3 21

,3 c, 12:58:G 04-01-85 ELECTRICAL MAINTENANCE MONTHLY REPORT FOR MARCH' PAGE 5 ETE.... COMPONENT..... FAILURE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION........ MR.NO..

2P DISTRIBUT!DN PANEL A-3 MI6.20 AMPS WERE 2.5 UNIT 2 AB ELEVATION 669 SHOWS CIRCUIT 42P NOT I

HEATING _ . , _

t, ' ~

03-27 0-BKRA-031 FOUND BREAKER DEFECTIVE DEFECTIVE BREAKER REPLACED DEFECTIVE A510144~

~

ON PMT-31 0F FIFTH VITAL ~ BREAKER BATTERY ROOM DUCT HEATER B -

.'03-27-85 0-LOCL-013-061 TROUKE ALARM KEEPS = CORR 0SION FOUND ON REPLACED DETECTOR A535177

-0 COMMING IN ON PYROTRONICS TERMINALS OF DETECTOR, XS-161-D IN ZONE 139-FANEL 610 PROKEM CAUSED BY WATER PANEL 610 _

CONDENSATING IN CONDUIT 03=27-85 2-MTRB-067-049 FILTER STAYS IN 2-FDIS-67-491B/A OUT OF RECALIBRATED A301053 1-A CONTINUOUS ON STRAINER CALABRATION 2-PDIS-67-4918/A TROUBLE

-A-A 0F ERCW SCREEN SHOT WIRING USIN6 MI 6.20 I

BACKWASH SWITCH _ NO PROBLEM FOUND VALVE

~

WORKING PROPERLY AT THIS TIME .

03-27-85 0-HTCK-234-33P HEAT TRACE CIRCUITS 33P BAD HEAT TRACE CABLE REPLACED HEAT TRACE A520171 1 333 AND 33S ARE BAD AND NEED CIRCUIT-33F 1 33S LAID REPLACING WIRES BACK DOWN OF MIAI.

12 CHECKED OPERATION OF -

CONTROLERS 33P IS FULLIN6 9 AMPS 33S IS

~ ~ '

PULLINO10AMPSDIDNOT CHAN6E WRAPS ON CT THE LIGHTS ON FANEL DID NOT

~

COME ON

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~

i .

- C RECORDS LISTED.

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1* J ? *~

ELECTRICAL MODIFICATIONS-SECTION a

MARCH 1985

-DCR 1739 - Insta11ationtof the VAACS Computer 1

'The CPU has been energized. . Diagnostics is in process. '

ECN 5024 - Installation of the Steam Generator' Lay-Up Water System. ^+

'l L Installation of piping insulation continues.

.ECN 5119 - Installation of'the Radiation Monitoring Cables in conduit.

. Conduit installation is 80. percent complete. Cable pulls have commenced.

.ECN'5194 --Iodine Monitors .

>- q

~

Security'partsfand phones are on order. Waiting for Power Block reconfiguration

to-place doors into the security system.

5 ECN 5200 - bait 1 Postaccident Sampling Facility

' Rework of the postmodification test deficiencies is in progress.

ECN '-5202 - Fifth Diesel Generator

" Workplan to install breaker and hot up the building is available for work.

There is come CONST' wark required prior. to placing bui1 ding on permanent power.

-ECN 5237- Laundry Facility Installation of-pre',sure switches,' temperature switches, and phones is in progress. Radiation monitor work'in the main control room'is complete.

ECN 5484 - Installation of Power Outlets in the Ice Condenser This work is complete for Unit 1.

'ECN 5495 - Field Services Building

. The building has' been placed on permanent power. Work on the fire detection system is in_ progress.

ECN 5565 - Inplant Repeaters The radio recombiner has been installed. The addition of a third general use channel-is' complete. This ECN is complete.

W 23

. ; ee O-ELECTRICAL MODIFICATIONS SECTION

' IE (Continued)

EtX 5664 - Replacement of the Relays in the Wells Fargo Alarms

' Remaining work is in hold until Construction abandons'the cables at the -

-ERCW pumping station.

ECN 5845 - Delete Nuisance Alarms

-This ECN'is complete.

ECN 5874 --Add Oil System on the RCP Motors:

Workplan writing is in progress.

ECN 5881 - Replace Limit Switches Workplan is ready for work during the ice outage.

ECN 5883 - Replace Flow Switches and Various Other Instruments

. Pressure' Switch workplan remains in the approval cycle.

ECN 5898 - Revise Limit Switch Logic Pre-outage work is complete.

'ECN 5970 - Replace Valve Operators

.All pre-outage operators have been changed out.

ECN 6032 - Relocate Hydrogen Analyzers All pre-outage work is complete.

ECN 6057 - Cable Tray Covers Approximately_240 out of 290 cable tray covers have been remanufactured or replaced.

ECN 6200 - Relocate Mainsteam Pressure Transmitters Work has commenced.

ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation is complete. Waiting for a Tech Spec change to place the circuits in operation.

ECN 6207 - Install Moisture Seals and Conduit Seals Workplan writing is in progress.

24

(

a .. .> '

i. ' ELECTRICAL-MODIFICATIONS SECTION

.(Continued)

Appendix R

.ECN 6209 - Wrap Fire Protective Blanket Around Conduit IApproximately:70 percent of the conduits assigned to this ECN have

.been wrapped.

'ECN 6235 - Reroute Various Cables The first.workplan is being written.

ECN '6260 - Wrap Conduits .

~

-. Work is' complete.

ECN 6316'- Seal for. Penetrations

~

Work is approximately 30 percent complete.

b u

a 25

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t

..ae INSTRUMENT MAINTENANCE

.1 Unit 1 ' ' " ' : .-

~

1. Performed monthly calibration of UHI level switches, SI-196. One switch 1-LS-87-22, was out of tolerance. PRO 1-85-93 was written.

~

2. Westinghouse completed the recalibration of RVLIS instrument racks.

3. The system 30 containment pressure transmitters PDT-30-44 and -45

, were replaced with qualified Barton model 764s. The old transmitters were Foxboro model E11GMs. scaled -1 to 15 psig. The presently installed ,

Bartons~are scaled -1 to 17 psig which required a complete rescaling of the instrument loops and replacement of the scaler on the control room j

~~

indicators. _

4. The commitment to NRC to delete the reset function on the SI block switches was extended to allow the modification to be performed during.

the ice outage.

l 5. NCR SQNNEB 8403 stated that the useful life of the containment H2analyzerb ._

would be limited during a LOCA due to the calayst being poisoned by large concentrations of iodine. To correct this deficiency the vendor supplied j a capsule containing a larger quantity of catalyst. The new catalyst

- capsules were installed in both trains A and B. Subsequent testing revealed that.the diffusion time for gas to pass through the catalyst increased the hold period for each calibration point from five minutes to 45 minutes.

A previous analysis by site services showed that the original catalyst was adequate. The analysis that generated the NCR was based on a large i BWR with higher iodine concentrations than SNP. Train B has been returned i to the original catalyst configuration to reduce out of service time for calibration and functional testing. Train A catalyst will-be returned to its original configuration in the near future.

[

6. The calibration of the new water treatment instruments in system 928 is approximately 90% complete.

• Unit 2 l

l 1. Performed monthly calibration of UHI level switches, SI-196.2. All switches were within tolerance.

t -2. .The calibration of the RVLIS racks is still in progress. Unit 2 calibration is being handled by Instrument Maintenance.

3. The -system 30 containment pressure transmitters PDT-30-44 and -45 were replaced with qualified Barton model 764s. The old transmitters were Foxboro model E11GMs scaled -1 to 15 psig. The presently installed Bartons are scaled -1 to 17 psig which required a complete rescaling of the instrument loops and replacement of the scales on the control room indicators.

O

c-5 : ,, ;>

o~"

• INSTRUMENT MAINTENANCE Unit 2 (Continued)

-4. -Deletion of'the reset function on the SI block switches was completed-by -

WP-11519. This satisfied thel commitment made to NRC for unit 2.

L5. A correction factor of 1.6% was entered into the P250 to.. compensate feedwater flow error due to fouling in the feedwater nozzle.

6. Recalibrated NIS Intermediate Range drawers for new core data per RTI-8.

Nu 27 1

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04-03-85 l .INSTRt31ENT f1AINTENANCE F10NTit Y SurRIARY. PAGE 1

! C0 RIP

'Q l T1R.C0r1P U FUNC SYS ADDRESS. DATE.... DESCRIPTION..................................... CCRRECTIVE ACTION...................... P ~

A102996 2 PT 003 122A 03/22/85 2-PT-003-122A. VERIFY CALIB 0F 2 PT 3122A LOOP PRESS. TRANSt1ITTER W45 F0t#6 0UT OF TO BE UITHIM TOLERANCE. REQ'D FOR PffT 53 RETEST - CALIB ON THE LOW SIDE OF TOLERANCE.

CN APPROX 3/27/85 PRESS. TRAt Cr1ITTER WMi RECALIB -

A103000 2 PT 003 132A 03/27/85 2-PT-003-132A, VERIFY CALIB PRESS.. TRANSF11TTER W45 FOUPO SLIGHTLY OUT OF CALI8 DN TIE LDU SIDE OF

. TOLERANCE. PRESS. . TRANSr11TTER WAS RECALIB.

A243492 1 PCV. 001 12 03/21/851-PCV-001-12, REGULATOR IS LEAKING AIR IN AN . GASKET ON TtE VLV POSITIONER WAS EXTREr1E (1ANNER LEAKING. CASKET ON TE POSITI0tER WAS REPLACED;T}E VLV WAS STROKED; ANO RETURNED TO SERVICE A2849/8 2 XX .092 5003 03/25/85 2-XX-092-5003,RECALIB HIGH LVL AFD ROD STOP ' HONE;RECAL PER RTI 8-RECAL TO NEW BISTABLES PER RTD 8 DATA SETPOIllT =

A25-7979 2 092 !C04 03/25/35 2-092-5004,RECALIB HIGH LVL AND ROD STOP NCIE;RECAL FER RTI 8-RECAL TO NEW ~

BISTABLES PER RTI 8 DATA SETPOItiT A299184 2 099 SSPS 03/02/85 2--099-SSPS. SUSPECT CLOCK.PRC8LEtts WITH SSPS. BAD ISOLATIO?1 BOARD-REPLACED BAD BOARD TRAIN 8 TO CarPUTER Rf1 A299241 2 XI 092 50058 03/04/85 2-XI-092-5005B,% FULL PWR FIETER READING HIGl IHO. DUT OF CAL. . REC 4. IND.

w N

> 7 records listed.

I I  !

=.

a .. a 1 i*' [ $ ' - -Machinical Mnintantnce Section

~

March 1985 Unit 0; -

J1. Repairs were made to the potable water-line in the diesel building.

., ' 2 .' A temporary demineralizer PVC line was repaired.

~

3. "H"~ waste gas decay' tank relief valve was repaired.

4. Replaced the acid pump in the temporary demineralizer.

5. Replaced.the bearing' lube water strainers to the cooling tower lift pumps,.2-A & 2-B.

6. Replaced the EHC filter caps.

Unit 1

1. . Investigating the low discharge pressure on IB-B fire pump.

'2k Repla,ced 1A-A fire pump.

3. . Replaced the lube oil cooler on IA-1 diesel engine.

4. -Replaced the belts on the IA-A 6.9 kV shutdown board room air handling unit.

, Unit 2

1. . Alinged 2-B stator cooling water pump.

2.- Replaced the gasket on the B-B auxiliary air compressor to correct a cover plate leak.

3.1 . Pulled the 2B-B fire pump to change-out the motor.

4. Changed-out the 2B-B seal water injection filter.

5. Rerouted the drain lines on the main turbine oil tank vapor extractor discharge.

6. Repaired the B gas stripper feed pump.

7. Replaced the inboard seal on 2A-A centrifugal charging pump.

28

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• M ch=nien1 M-dificctirn Section March 1985 ECN 2780/5200 - Post Accident Sampling Facilities Minor replacement / repair parts were received and installed.

ECN 5938 - Feedwater lleaters X-raying of the #4 heaters was completed without repairs. Work continues on the reinforcing of the nozzles on the #3 heaters. Installation of the mono-rails and various support steel continues. Additional pipe reroutes for access was completed.

" Appendix R" ECN 6319 -

Two workplans for plugging and relocating sprinkler heads were placed in the approval cycle.

ECN 6311 -

A. The workplan to clear deficiencies associated with the open penetrations in the Auxiliary Building general areas on El. 714, 690, 653 was written and worked. This item should be completed.

B. The valve operator extension was started under the workplan to core drill the valve room wall.

ECN-5373 -

Con Demin Air Compressor - The mechanical work was completed.

Insulation and painting activities are in progress. Upon completion of the electrical work a vendor representative will be here for start-up testing.

ECN 6328/6356 ERCW Flange and Reducer Replacement - Upon removing the first reducer, it was discovered that the flanges had degraded also.

ECN 6356 was issued, a workplan prepared and was approved.

Replacement of the flanges and reducers is continuing.

ECN-0588 - 6032 - 112 Monitor Relocation: A decision was made to procure WBNP's monitors to install them at Sequoyah in the new location.

This will reduce the work required to be performed during the ice outage. Sequoyah's monitor will be returned to WBNP.

6231 - Relocation of pipe and hangers for motor operators. One hanger workplan was worked. The piping reroute workplan remains in the approval cycle.

Component lleat Exchanger Replacement. Review of various options continues.

A trip to Salem Nuclear Plant was made by modification, site services, and maintenance personnel.

MSR Tube Bundle Replacement. Efforts continues in finalizing the work to be done and the evaculation of various options.

Ice Outage - Planning & Scheduling Activities continues.

ECN 5009

- ERCW Piping Replacement - Work was started on the replacement of piping to the AEW boric acid room cooler. SI-566 was started with the results dictating future work and scheduling.

in N

sE .

C 3 - _ - , . _ ,

)

+ - TENNESSEE ' VALLEY. AUTHORITY

.Sequoyah Nuclear Plant

_ :P. O. Box 2000 i 3

ic , Soddy-Daisy, Tennessee. 37379 1

I .:

~

Li ' April 12, 1985

Nuclear Regulatory Commission

~ Office of.ManagementiInformation.

and Program Control 4

, l Washington,DC '20555

^

Gentlemen:

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

Very truly yours,

. TENNESSEE VALLEY' AUTHORITY J

P. R.:Wallace

, -Plant Manager Enclo'ure-a

, 'ce' (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, CA 30323-(1 copy) INPO Records Center Suite 1500

.7 . Director, Office of. Inspection 1100 circle 75 Parkway and-Enforcement .

Atlanta, GA 30339 (1 copy)

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 e P. O. Box 355 '

Pittsburgh, PA. 15230 (1 copy)

E. J. Ford, NRC Inspector, NUC PR, Sequoyah 4 -

f c

q 1983-TVA 5OTH ANNIVERSARY l An Equal Opportunity Employer

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