ML20071G667

Monthly Operating Repts for Apr 1983

ML20071G667
Person / Time
Site:	Sequoyah
Issue date:	05/09/1983
From:	Dupree D, Mason C TENNESSEE VALLEY AUTHORITY
To:	NRC
References
NUDOCS 8305240323
Download: ML20071G667 (24)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT APRIL 1, 1983 - APRIL 30, 1983 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 i

l i

l Submitted By:

Powar Plant Superintendent I

l 0305240323 830509 l

PDR ADOCK 05000327 l

R PDR

- =__.

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4 TABLE OF CONTENTS Operations Summary............

.1 Significant Operational Events

. 1-4 PORV'r and Safety Valves Summary.....

.5 Licensee Events and Special Reports

. 5-6 Offsite Dose Calculation Manual Changes

.6 Operating Data Unit 1

. 7-9 Unit 2

. 10-12 i

Plant Maintenance Summary

. 13-20 I

l

= _.

.w Op* rations Sumaary April, 1983 The following summary describes. the significant operational activities i

for the month of April.

In support of this summary, a chronological log of significant events is included in this report.

Unit 1 Unit 1 was critical for 719 hours0.00832 days <br />0.2 hours <br />0.00119 weeks <br />2.735795e-4 months <br />, produced 824,830 MWH (gross),

j resulting in an average hourly gross load of 1,147,191 kW during the month.

There are 201.91 full power days estimated remaining until the end of cycle 2 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached December 25, 1983. The capacity factor for the month was 98.6 percent.

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

i Unit 2 Unit 2 was critical for 719 hours0.00832 days <br />0.2 hours <br />0.00119 weeks <br />2.735795e-4 months <br />, produced 829,530 MWH (gross),

resulting in an average hourly gross load of 1,153,530 kW during the month.

i There are 78.61 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached August 1, 1983. The capacity factor for the month was 99.2 percent.

There were no reactor scrams, no manual shutdowns, and one power reduction during April (a continuation from March).

Significant Operational Events Unit 1 Date Time Event 04/01/83 0001 Reactor in mode 1 at 100% power pro-ducing 1190 MWe.

f 04/02/83 0530 Began reducing load for the turbine acceptance test.

0956 Reactor at 60% power. The cards were pulled on #2 and #3 governor valves.

1040 Began power ascension. l - - -.

~,.

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l Significant Operational Events Unit I (Continued) l l

Date Time Event 04/02/83 1410 Reactor at 75% power producing 883 MWe.

1715 Began reducing load to replace the cards in #2 and #3 governor valves.

1826 Reactor at 62% power producing 725 MWe, 1838 Began power ascension.

04/03/83 0100 Reactor at 100% 1180 MWe.

04/08/83 0838

1. 3 governor valve closed for the turbine acceptance test. Reactor at 100% power producing 1163 MWe.

1440

1. 1 throttle valve was found only 10%

open, reactor at 92% power.

1900

1. 3 governor valve reopened.

2030 Reactor at 100% power.

2107

1. 1 throttle valve card replaced valve full open.

04/09/83 0630 Began reducing load for the turbine acceptance.

0910

1. 2 and #3 governor valves closed.

Reactor at 75% power.

l 1650 Governor valves reopened, began l

power ascension.

l l

2115 Reactor at 100% producing 1190 MWe.

04/12/83 1450 Began reducing T-avg for the turbine acceptance test.

i 1510 Reactor at 98% power.

1935 Began power ascension.

l l

2220 Reactor at 100% power producing i

1186 MWe.

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l l i

I

Significant Operational Ev:nts Unit 1 1

l (Continued)

Date Time Event 04/13/83 1018 Reduced T-Avg for the turbine acceptance test.

1419 Reactor at 98% power producing 1180 MWe.

1910 Began power ascension.

2215 Reactor at 100% power producing 1186 MWe.

04/14/83 1615 Began reducing load for maintenance on #3B heater drain tank pump.

2035 Reactor at 75%.

04/15/83 0247

1. 3B heater drain tank pump maintenance completed, began power ascension.

1420 Reactor at 100% power producing l

1190 MWe.

04/24/83 0200 Switched from standard time to daylight savings time.

04/30/83 2359 Reactor in Mode 1 at 100% power producing 1190 MWe..

l Unit 2 l

Date Time Event l

04/01/83 0001 Reactor in Mode 1 at 75% power producing 918 MWe.

Incore/excore calibration in progress.

1200 Began power ascension l

1800 Reactor at 98% power, producing 1171 MWE.

1. 3 governor valve closed.

04/06/83 1127 Reduced load for SI-139. Determination of the at power moderator temperature coefficient..

)

N-Significant Opersticnal Events 1

Unit 2 (Continued) 1 Date Time Event 04/06/83 1133 Reactor at 94% power producing 1145 MWe.

1152 Began power ascension 1157 Reactor at 98% power producing 1170 MWe.

1212 Began reducing load for SI-139.

1217 Reactor at 94% power producing 1145 MWe.

1237 Began power ascension.

1245 Reactor at 98% power producing 1179 MWe.

1305 Began load reduction for SI-139.

1310 Reactor at 94% power producing 1145 MWe.

1315 Began power ascension 1320 Reactor at 98% power producing 1170 MWe.

1322 Reducing power for SI-139.

1327 Reactor at 94% producing 1145 MWe.

1342 Began power ascension.

1345 Reactor at 98% power producing 1170 MWe.

l 1352 Reducing power for SI-139.

l 1357 Reactor at 94% power producing 1145 MWe.

1402 Began power ascension.

1407 Reactor at 98% power producing 1170 MWe.

SI-139 complete.

04/24/83 0200 Switched from Standard Time to Daylight Savings Time.

l 04/30/83 2359 Reactor in Mode 1 at 98% power producing 1170 MWe.

1. 3 governor valve closed....

~

e PORV'S and Safety Valvas 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 April 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

Unit 1 LER SUBJECT SQRO-50-327/83045 No. I steam generator wide range level channel failed low due to defective switches in the connector of recorder 1-LR-3-43.

SQRO-50-327/83047 Reactor coolant system subcooling margin monitor declared inoperable due to the plant computer failing due to memory parity error.

SQRO-50-327/83048 During review of SI-111 performed 09/11/82, safety relief valves 1-RV-1-512, -513, -518, -515, and

-521 did not meet the required setpoint criteria.

During the performance of SI-111 on 01/08/83 safety relief valves 1-RV-1-525 and -527 did not meet the specified setpoint criteria.

es SQRO-50-327/83049 Ice condenser intermediate deck door in bay 11 found frozen closed.

Ice resulted from leaks in the condensate drain lines of AHU 13 and 14.

SQRO-50-327/83052 During the performance of SI-196, ' Valve Closure Verification Test of Upper Head Injection System Hydraulic isolation Valves', 2 of 4 level switches were out of tolerance on April 7, 1983.

SQR0-50-327/83053 On 03/19/83 steam generator blowdown isolation valve 1-FCV-1-14 would not stay open and the post maintenance stroke test was not accomplished.

I SQR0-50-327/83054 Containment isolation valve 1-FCV-1-182 failed to

)

open during the performance of special test SQ-STEAR-INST-83-03.

Unit 2 SQR0-50-328/83044 UHI level switches LS-87-21, -22, -23, -24 found

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out of tolerance during the performance of SI-196 on March 24, 1983.

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Licensse Evsnts and Special Rrports (Continued)

Unit 2 LER SUBJECT SQR0-50-328/83046 Reactor coolant system subcooling margin monitor was declared inoperable due to the plant computer failing caused by a faulty area on the disc.

SQR0-50-328/83050 Control rod D-8 failed to move with the rest of the bank upon demand and became misaligned more than 12 steps. Troubleshooting indicates a lift coil inoperable due to a loose connector at the vessel head.

SQR0-50-328/83051 2-FCV-63-40 BIT inlet isolation valve would not operate during the performance of SI-166.1 due to dirty contactors in the motor starter.

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

Offsite Dose Calculation Manual Changes There were no changes to the ODCM during the month.

UNIT SHUTDOWNS.AND POWER REDUCTIONS DOCKET No.

50-327 UNIT NAME Seauovah one DATE May 8, 1983 COMPLETED BY M. Eddings REPORT MONTH APRIL TELEPHONE _ (615) 870-6543 W

O 8g "e

c yt T.f,censee y

Cause & Corrective No.

Date 8.

O 's 8

'808 Event 8%

Action to y

2e 8

5y*

Report #

g'8 8, '8 Prevent Recurrence 5"

N" 8"

15.

830402 S

0 B

5 STEAR Test on the Turbine.

4 16.

830409 S

O B

5 STEAR Test on the Turbine.

17.

830414 F

0 B

5 Maint on 3B heater drain tank pump..

b 1

2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions l

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 E-Operator Training & License Examination 4-Cont, of Existing 0161)

F-Administrative Outage 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.

50-327 UNIT 1

DATE May 3, 1983 COMPLETED BY D. Patterson TELEPHONE (615) 870-6543 MONTH APRIL DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1143 17 1141 2

941 18 1141 3

1136 1140 19 4

1143 20 1140 5

1139 21 1140 6

1136 22 1140 7

1141 23 1142 8

1111 24 1144 9

989 25 1142 10 1146 26 1140 11 1141 27 1141 12 1145 28 1140 13 1142 1137 29 14 1059 30 1136 15 1085 31 N/A 16 1141 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

(9/77). _ _ _ _.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-328 UNIT NAME Sequoyah Two DATE May 9. 1983 COMPLETED BY David Dupree REPORT MONTH APRIL TELEPHONE (615) 870-6543 q

l W

o gg e @f y Licensee y

Cause & Corrective Ne No.

Date 8,

O8 g

'8 0 g Event g *,

g *,

Action to y

Cj g

5y*

Report !

g'g 8,*g Prevent Recurrence E"

?@$

0" e

9 830330 F

0 B

5 Incore/Excore calibration, RX@ 75%.

(Continuation of previous reductions.)

s i

1 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5

(9/77)

H-Other (Explain)

Exhibit I-Same Source

T AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-328 UNIT 2

DATE May 9, 1983 COMPLETED BY David Dupree TELEPHONE (615) 870-6543 MONTH APRIL DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 968 17 1119 2

1121 18 1117 3

1122 19 1118 4

1121 20

.1120 5

1109 21 1119 6

1116 22 1116 7

1119 23 1121 8

1114 24 1121 9

1120 25 1119 10 1120 26 1117 11 1118 27 1125 12 1117 28 1121 i

13 1121 29 1122 l

14 1119 30 1121 15 1121 31 N/A 16 1119 l

t INSTRUCTIONS i

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

(9/77) l,

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a

OFEMII!S CAIA F991

~

DCC ET FS. 50-328 DAIE 5-? o3 Tf1ETElf SY D.C.ItJC*EE TELEPH0tE (6151870-6543 OPERATING STATUS

1. LNIT No"E: SEC8J0Yff! NJC1EA*. ftffli, LHIT 2 HeiES:

2. REPORT PERIOD: feRIL 1 THRU 20,1083

3. LICENSED TEFM1. POWER (PHI):

3911.0

4. NAEPLATE PATIE (0ROSS MAE):

1220.6 5, DESIC+! ELECTRICAL PATING (ET M):

114?.0

6. MIIMJM CEPENDAELE CffACITY (0ROSS MNE):

lit?.0

7. If.IIMLM DEPENDAELE CAPTCITY (tET MWE):

112?.0 8, IF CWe!CES OCCtR IN CAP / CITY MTIES(!TE!?? N'JM?E S 3 THRC8)C41 7)SINCE LAST PEc0RT, OIVE FEASONS:

9. POWER LEVEL TO !*i!CH FESTRICTED,IF ANYINET f6'E):

10. PSENS FOR FESTRICTICES>lF Mf:

THIS HONTH YR.-TC-CATE CUlf)LATIVE

11. HOURS IN PiPORTING PERIOD 71?.00 2879.00 S016.??

12. NUMBER OF HOLRS PSETOR !1AS CRITICAL 71 **

• 'n 6754.?2

13. PEACTOR PESEfNE SMJTDOWN H0lRS 0.00 0.00 0.00

14. HOURS GENEPATOR ON-LIFE 710.M 2S31.40 643?.15

15. LWIT ESERVE SHJTDCHN HOURS 0.00 0.00 0.00 16., OROSS theft"AL EMER0Y GENEMIED (MWH) 2t!!55?.45 *2723*5.02 21439 '6.32

17. 6c.0SS ELECTRICAL EEP0Y CfN. (M!*f)

E?O.M 3202030.00 7284780.00

!S, ET ELECTRICAL EER0Y CENEFATED (!W.! 89593.00 303?S?3.00 70!617?.60

17. UNIT SERVICE FACTOR 100.00 o?.?S 82.81 20, UNIT AVAILAEILITY FACTOR 100.00 c?.33

?2.81

21. lHIT CAPACITY Ff4TCR(USING MDC NET)

?.7!

95.15 77.60

22. UNIT CAPACITY FfCTOR(USING IER PET) 96.?C

?3.19 76.24

23. lHIT FORCED E9)TAGE PATE 0.00 1.65 10.*?

24. SNJTDOWNS CErnJLED DVER NEIT 6 MCHTHS (TLcE, DATE. AND Ct.'RATItH W EfCH):

Rifncling.ontage to beeiIL_apyroximately__A_u_ gust 5,__1983.

l 25. IF S9JTDR! AT END 0F REFORT FERIOD, ESTIMTED DATE OF ETARTUc:

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j 19TE TMT T'-!E IE YR.-TO-CATE ff0 CUM'JLATIVE VitVES M"c cc:" '* COTED.

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e Plant Maintenance Summary The following significant maintenance items were completed during the month of April 1983:

MECHANICAL MAINTENANCE 1.

Repaired a steam leak on level switch 2-LS-6-104B on No. 3 Heater Drain Tank, Unit 2.

4 2.

Repaired leaks on letdown radiation monitor 1-RE-90-104, Unit 1.

3.

Installed the rebuilt condenser vaccuum pump IC.

4.

Rebuilt & replaced parts on auxiliary air compressor "A".

5.

Installed the cooling tower blowdown radiation booster pump and cooling tower blowdown flow transmitter.

6.

Installed a temperature control valve on the glycol chiller room cooler.

7.

Installed a temporary line to the ERCW station from the Hypochlorite Building to inject hypochlorite to the ERCW Pump Pits.

Electrical Maintenance 1.

Continued installation of the Dimension 2000 phone system.

2.

Continued systematic walk down and inspection of the E-field wiring and made necessary repairs.

3.

Continued repairs on paging system to fulfill INP0 commitment.

4.

Continued modification work on the spare RCP motor upper bearings.

5.

Began major repairs on the CTL pump 1B motor and added new sight-glass to oil reservoirs of several other CTL pump motors.

t 6.

Repaired transformer cooling fans.

7.

Continued repairs on 6.9 kV SD BD breakers.

8.

Painted in plant DI sand filter A.

9.

Investiaged D-8 control rod drive problem on Unit 2.

10.

Completed repairs to the Unit I and Unit 2 heater drain level switches.

l l t

= - -

Plant Maintenance Summary l

(Continued)

Instrument Maintenance 1.

Continued monthly calibration surveillance on the Unit 1 and 2 UHI level switches. Two of the four switches were found out of tolerance on Unit 1 on April 7, 1983 and three of the four switches were found out of tolerance on Unit 2 on April 21, 1983. A new calibration procedure was used on Unit 2 which resulted in no switch being more than.9' H O out of tolerance.

2 All switches were returned to service after the surveillance was completed.

Expecting Tech Spec change by next month's report.

2.

On Unit 1, control bank D failed to move on demand after receiving a rod control system urgent alarm.

Initial indication was a phase failure in the lift circuit of power cabinet IBD. The problem was found to be the "C" phase reference voltage fuse (FU-10) blown. The fuse was replaced and rod control system verified operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

3.

Completed removal of the status monitoring system.

4.

Completed modification on the fuel handling fan damper controls in an effort to improve the auxilliary building pressure control problem. This 4

continues to be a problem in the fact that the pressure controllers are not designed to recover from a transient condition such as aux. b1dg.

isolation. DCR 1717 will need to be completed before this problem can be resolved.

5.

Aux. feedwater level control valve 2-LCV-3-156 failed during performance of SI-276. The valve would not travel full open on demand.

Investigation found that the valve positioner installed was for a 3-15 psi output and should have been for a 60 psig supply pressure. An inspection was made for both units and found one other positioner for 1-LCV-3-164 to have the incorrect range specified on the nameplate data. Both positioners were changed l

out by ones obtained from WBNP unit 1, verified operable, and returned to service. The valve on unit I was operable at the time of changeout and had not experienced any ctroke problems.

6.

Initiated draft revisions for surveillance test to extend the time interval required to conduct analog channel functional test of the engineered safety l

features and reactor trip systems from one month to three months per a Technical Specification change.

'7.

Removed 75% of the Oak Ridge National Lab online analyzer. Will complete removal next month.

8.

Replaced the Hathaway data logger printer in main control room with a new DEC printer.

I t

- - _, _ - ~

~

Plent Mnintanence Summary (Co'ntinued) 9.

Unit 1 EHC #1 throttle valve started drifting closed serveral times.

Found problem on valve test circuit card which could not be repaired on line. Jumpered output to keep valve from closing on its own. This did not affect any normal or safety functions of the valve, only the test circuit output.

10.

Started working on remaining initial instrument calibrations and loop test to be done on the CDWE system.

Field Services Group 1.

ECN 5510--Containment Personnel Airlock Penetrations (Units 1 and 2)

Post-modification functional testing and adjustment of the containment personnel airlock door annunciation limit switches for both units was conducted this month. The unit I switches functioned satisfactorily.

Work is continuing to adjust the unit 2 switches.

2.

ECN 5634--High-Pressure Feedwater Heater Solenoid Relief Valves (Units 1 and 2)

Painting of hangers has been completed and insulation work is continuing.

3.

ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2)

The installation of conduit and junction boxes is continuing on elevations 706 and 714 in the auxiliary building. Core drilling in the auxiliary building along the A5 line wall is completed and two sleeves have been installed. Grouting of these sleeves is in progress. Pefabrication of the HVAC ductwork serving the PASF area is continuing and some ductwork has been installed.

Installation of HVAC equipment serving both units is in progress in the PASF area.

The installation of component cooling piping to the PASF coolers on unit 2 is in progress. The component cooling piping tie-in to the system will require a unit outage. Work is continuing to install the post-accident sample tubing in the unit I room. Work has begun to insall the unit 2 post-accident sample tubing with work concentrating in the unit 2 annulus. Work is also underway to fabricate the steel containment vessel penetration plates for the post-accident sample tubing to the primary containment. Tie-in of the demineralized water piping serving the unit 2 PASF equipment

.to the demineralized water system is scheduled to be made soon.

This will complete work on this portion of the PASF..-.

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Plant Maintenance Summary (Continued) 3j 7

1 4.

ECN 5096--Common Station Service Transformer (CSST) "C" Cable pulling is continuing to 161-kV switchyard bay 7 and 14, and CSST "B" with approximately 95 percent of the work completed.

s Termination and lay down of control cables for the CSST "B" has begun and is approximately 10-percent complete.

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• I 5.

ECN 5429--Containment Hydrogen Mitigation System (Unit 2)

Installation of conduit and junction boxes in upper containment t

(excluding the ice condenser) has begun. Fabrication of hanger supports for conduit in the ice condenser is in progress and approximately 75 percent complete.

Installation of conduit of elevation 759 in the auxiliary building is in progress. Preparation for installing the hydrogen mitigation system electrical equipment and annunciation in the. control and auxiliary buildings is underway.

l 6.

ECN 5009--ERCW Piping Changeout (Units 1 and 2)

Fabrication of small diameter ERCW piping serving the penetration s

room coolers 2A1, 2A2, 2A3, 2B1, 2B2, and 2B3 was completed during April.

Installation of piping for the unit 2 "B" train penetration room coolers is in progress.

7.

ECN 5645--Steam Generator Blowdown Heat Exchangers This ECN is to install first and second stage heat exchangers in the steam generator blowdown system for both units 1 and 2.

Installation of piping and hangers is continuing for the unit I heat exchangers but bi );

has been delayed because of the lack of sufficient hanger design.

Fabrication and installation of piping, hangers, and flow elements on i

elevation 662 of unit 2 turbine building is in progress.

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8.

ECN 5451--Diesel Generator Engine Lube Oil System Work performed this month was the functional testing of oil pumps and pressure switches.

9.

ECN 5104--Main Steam Reheater (MSR) Steam Bypass (Unit 1)

The frames are installed for the extension of the three MSR housings (dog houses) around the newly installed MSR steam bypass pipes.

t Fabrication of the housing sheetmetal covers is complete, but installation of the covers will be delayed until all work associated s

l with bypass valves is completed. All conduit serving the MSR bypass s

i valves is installed.

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Plant Maintentace Summary (Continued) 10.

ECN 5495--FSG Office Building Power Supply Work required for occupancy of the new building was completed this month. Installation of miscellaneous and communication cables for the building is continuing.

Cale trays are being fabricated for installation in the turbine building.

11.

ECN 5106--Reactor Vessel Level Indication System (Units 1 and 2)

Work is continuing to install conduit outside the reactor building.

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The majority of this conduit that.can be installed at this time is in place. Work has begun to install cables for this system outside containment as well.

4 12.

ECN 5237--Laundry Room Improvements Work is continuing to install the remaining laundry room equipment and associated mechanical systems. All equipment hac been placed in position except for the washing machine and sink which are currently awaiting installation of the drain serving this equipment. Remaining work includes extensive modification of the laundry room ventilation system, building a masonry divider wall, and completion of all condrit and power calbes serving the facility.

13.

ECN 5596--Install Batch Neutralization Tank Piping and hanger installation is continuing unimpended in the turbine building with an overall completion estimate of 40 percent.

There has been 99 of 175 feet of 6-inch pipe, 126 of 260 feet of 3-inch pipe, and 60 of 275 feet of 1-inch pipe installed.

14.

ECN 5198--Locate and Design A Technical Support Center (TSC)

The TSC room is structurally complete as the drop ceiling has been installed and touchup to the floors and walls is complete. All HVAC system work in the TSC room is complete and work on this system in the existing relay room is nearing completion. The fire protection sytem piping is completely installed in the TSC room, but work remains to be completed in the relay room. Lighting for the TSC area is complete except for miscellaneous work items to finish the system installation.

The major work remaining in the TSC room is installation of the fire detection system, computer terminals, and carpet.

Work is scheduled to continue throughout the spring and summer to install electrical equipment, conduit, and cable for the TSC.

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Plent Maintenance Summary

(' Continued) 15.

FCN 5460--Reroute Auxiliary Feedwater Pump Seal Water to Turbine Building (Units 1 and 2)

All mechanical work is complete to install this drain system. Final painting and gout touchup in the unit 1 auxiliary feedwater Yerry turbine pump room remains to be completed.

16.

ECN 5726--Reroute Feedwater Flow Sense Lines (Units 1 and 2)

All painting was completed during this reporting period. This completes this ECN.

17.

ECN 5642--Add N, Regulating Station To Supply N, To Deaeration Distribution System Inside Condensate Storage T5nks The nitrogen supply piping to the tanks remain in work between the new liquid nitrogen supply station and the condensate storage tanks.

l This piping is installed except for tie-in to the tanks, internal valve cabinet piping installation, and completion of the yard piping installation between the liquid nitrogen supply station and the unit 2 No. 1 valve cabinet. Conduit and cable installation began this month.

18.

ECN 5119--Radiation Monitors For Containment Isolation Waste Disposal System (Unit 1) i The rerouting of radiation monitor cables to place them in conduit for the condenser vacuum exhaust and steam generator blowdown systems was completed during this time period. This does not complete this ECN.

19.

ECN 2773--Install Radiation Detectors (Unit 2)

Work was completed this month to install radiation detectors, local indications, and conduit for the unit 2 condenser vacuum exhaust area monitors. Pulling of cables through these conduits is underway.

Installation of conduit for the unit 2 reactor building ventilation radiation monitor is in progress as well.

l l

Plant Maintenenca Sumanry (Continued) 20.

ECN 2923--RHR Lines Radiation Monitors (Unit 2)

Conduit installation and cable pulling for these monitors is nearing completion. Remaining work includes final cable pulling in the RHR pump rooms,' terminations at the monitors, and the main control room 1

panels 2-M-30 and 2-M-31 which are not yet installed.

21.

ECN 5582--Add N Regulating Stations To Supply N To Steam Generators This system is supplied with nitrogen by the same system that supplies nitrogen to the condensate storage tanks as discussed in this report (ECN 5642). In addition to the outstanding work described under the ECN 5642 portion of this report, the nitrogen piping inside the unit 2 main steam valve rooms remain to be completed as well as excavation and installation of the unit 1 yard piping.

22.

ECN 5248--Nitrogen Truck Fill l

This work is to relocate the nitrogen truck fill pipes from the north to the east side of the auxiliary building. All pipe hanger unistruts are mounted and the pipe fabrication is complete.

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23. ECN 5086--Turbogenerator Floor Handrails Installation of handrails adjacent to the Nos. I and 3 governor valves for both units 1 and 2 turbogenerators was completed this month.

24. ECN 5519--Plant Crane Escape Devices i

I Structural members used to attach the escape devices to the two turbine building cranes above the elevation 732 floor have been installed. These members are also to be installed on the polar cranes in the reactor buildings as soon as authorization is granted i

I to perform this work.

25.

ECN 5449--6.9-kV Shutdown Board Degraded Voltage Circuitry Work began this month to pull 20 cables between the following panels:

6.9-kV shutdown boards, 6.9-kV logic panels, main control room communication panel 1-M-21, and the auxiliary control room annunciation panel 0-L-4.

26.

ECN 5780--Upper Head Injection Water Accumulator Tank Sample Tubing Extension Work was completed this month in the additional equipment building to extend sample tubing from the upper head injection water accumulator tanks to newly installed sample sinks. This work was completed for both units this reporting period..

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P1 cat Mtintenance Summary

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(Continued) 27.

ECN 5607--Plant Overhead Door Control Circuitry The plant overhead door control circuits were modified during this reporting period but will not be functionally tested until completion of all maintenance on the doors.

28.

ECN 2775--Containment High Range Area Radiation Monitors Work began this month to pull cables outside containment for these monitors. Completion of the containment cable pulling, radiation detector installation, final conduit installation, and cable terminations cannot be accomplished until an outage period.

29.

ECN 5867--Fuel Transfer System Decontamination of the fuel transfer system was accomplished this month in preparation of modifications to the system equipment. Because of insufficient design information, this modification will only be partially implemented prior to the unit 2 cycle 1 refueling outage.

30.

LDCR 1847--Chemical Feed Injection to Condensate Polisher discharge All hangers have been installed and tubing installation is in progress for tie-in of the chemical feed system to the condensate polisher discharge piping. This job has an overall completion estimate of 45 percent.

31.

LDCR 1883--Liquid Nitrogen Station Excavation, form erection, and rebar installation have been completed this month in preparation for pouring the liquid nitrogen station concrete pad.

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-a TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Daisy, Tennessee 37319 MAY 13 ENI3

(

Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the April 1983 Monthly Operating Report for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE / ALLEY AUTHORITY C. C. Mason Power Plant Superintendent Enclosure cc (Enclosure):

Director, Region II Director, Office of Management Director, Office of Management Information and Program Control Nuclear Regulatory Commission Nuclear Regulatory Commission i

Washington, DC 20555 (2 copies) 101 Marietta Street Suite 3100 i

Atlanta, GA 30303 (1 copy)

\\

\\

Director, Office of Inspection \\

and Enforceme_nt

\\

Nuclear Regulatory Commission

,/

Washington, DC 20555 (10 copies)

Mr. A. Rubio, Director Mr. Bill Lavallee, NSAC 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)

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k An Equal Opportunity Employer l

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