ML20077H779

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Monthly Operating Repts for June 1983
ML20077H779
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/13/1983
From: Eddings M, Mason C
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8308110299
Download: ML20077H779 (20)
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.D TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION JUNE 1, 1983 - JUNE 30, 1983 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted By:

Pfwer Plant Superintendent 8308110279 830713 l

PDR ADOCK 05000327 R i PDR '

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o TABLE OF CONTENTS Operations Sununary . . . . . .. . . . . . . . . . . . . . . . . 1 Significant Operational Events . . ... . . . . . . . . . . . . 1-2 PORV's and Safety Valves Sununary . .. . . . . . . . . . . . . . 3 Licensee Events and Special Reports . . . . . . . . . . . . . . 3-4 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . 4 Operating Data Unit 1 . ... .. . . . .. ... . . . . . . . . . . . . 5-7 Unit 2 .... .. . . .. .. . . . . . . . . . . . . . . 8-10 Plant Maintenance Sununary .. . . ... . . . . . . . . . . . . 11-17 t

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Operations Summary June, 1983 The following summary describes the significant operational activities for the month of June. In support of this summary, a chronological log of significant events is included in this report.

Unit 1 Unit I was critical for 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />, produced 837,500 MWH (gross),

resulting in an average hourly gross load of 1,163,194 kW during the month.

There are 142.10 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 15, 1983. The capacity factor for the month was 98.3 percent.

There were no reactor scrams, or manual shutdowns, and only one power reduction occurred during June.

Unit 2 Unit 2 was critical for 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />, produced 755,050 MWH (gross),

resulting in an average hourly gross load of 1,048,681 kW during the month.

There are 20.21 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 July 24, 1983. The refueling outage is scheduled to begin on August 5,1983. The capacity factor for the month was 90.2 percent.

There were no reactor scrams, no manual shutdowns, and one power reduction during June.

Significant Operational Events Unit 1 Date Time Event 06/01/83 0001 Reactor in mode 1 at 100% power pro-ducing 1180 MWe.

06/04/83 0245 Began reducing power for maintenance on #3 heater drain tank level control valve air line.

0614 Reactor at 75% power producing 886 MWe.

1023 Began power ascension, i

2200 Reactor at 100% power producing 1174 MWe.

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Significent Oparaticnal Evznts

. Unit 1 (Continued)

Date Time Event 06/30/83 2359 Reactor in Mode 1 at 100% power -

producing 1165 MWe.

Unit 2 Date Time Event 06/01/83 0001 Reactor in Mode 1 at 98% power producing 1165 MWe. #3 governor valve is fully closed and control rod D-8 is inoperable.

06/09/83 0745 Began borating RCS to reduce reactor power so oil can be added to Reactor Coolant Pump 1.

1450 Reactor power at 32% producing 330 MWe.

1755 Began power ascension.

2100 Stopped power ascension due to delta flux. Reactor at 37% power producing 385 MWe.

06/10/83 0030 Began power ascension.

0600 Stopped power ascension due to delta flux. Reactor at 41% power producing 450 MWe.

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1300 Began power ascension.

1550 Stopped power ascension due to delta flux. Reactor at 45% power producing 495 MWe.

06/12/83 2315 Began power ascension.

06/15/83 0600 Reactor at 98% power producing 1160 MWe.

06/30/83 2359 Reactor in Mode 1 at 98% power

. producing 1160 MWe. #3 governor

-valve fully closed and control rod D-8 is inoperable.

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

Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during June 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

Unit 1 LER SUBJECT SQR0-50-327/83070 Diesel Generator IA-A was declared inoperable due to a oil cooler failure and cylinder head leak.

SQRO-50-327/83075 The kilowatt meter for the hydrogen recombiner showed no indication of power usage. GE silicon control rectifier model No. GEC50M failed due to a end of normal life.

SQRO-50-327/83076 Radiatior monitor 0-RM-90-225 was declared inoperable due to the loss of sample flow because the Dean Brothers pump model PH201 failed.

SQRO-50-327/83077 AFW valve 1-PCV-3-122 was delcared inoperable because it. failed to operate correctly. The hydraulic MOOG valve was found clogged and the hydraulic pump was worn causing the pump motor to fail on high amperage.

SQRO-50-327/83079 NCR SQNNEB 8304 states the possibility of a block wall failing during a tornado which could cause damage to the IE electrical boards. Incorrect load factors were used in the original calculations.

SQRO-50-327/83080 RPI D-14 on shutdown bank A was declared inoperable due to the indicator indicating greater than 12 steps from the demand counter.

l SQR0-50-327/83083 1-FT-30-242, Shield Building Flow Rate Monitor l was declared inoperable due to the sense line-being clogged.

SQR0-50-327/83084 1-LS-87-22 and -23 were found outside the allowable tolerance _for setpoints during channel calibration.

Channel calibration will continue on a 30 day basis until the drift _ problem is resolved.

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Licensee Evants and Special Reports Unit 2 LER SUBJECT SQR0-50-328/83073 During the performance of SI-205.2 Shield Shield Building Exhaust Gaseous Effluent Radiation Monitor 0-RM-90-100 was declared

, inoperable because the required output voltage levels could not be obtained.

4 SQRO-50-328/83074 RCS subcooling margin monitor was declared inoperable due to the failure of the plant process computer due to a power interruption.

SQRO-50-328/83078 Steam generator effluent line radiation monitor 2-RM-90-120/121 was delcared inoperable due to the loss of sample flow.

SQR0-50-328/83081 The upper containment airlock was found broken and declared inoperable due to two cam follower bearings failing on the operating mechanism.

SQRO-50-328/83082 2-FI-63-91C, Remote Shutdown Instrumentation Channel for the RHR flow rate was declared inoperable during the performance of SI-109 due to instrument drift.

1 SQRO-50-328/83085 On 06-14-83 the RCS subcooling margin monitor was declared inoperable twice due to the loss of the plant process computer. Once due to a power failure and the other time due to a blown fuse in the analog switch card.

SQR0-50-328/83086 2-FCV-1-32 was declared inoperable-when the valve closed and would not reopen. The valve operator diaphragm was found ruptured.

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

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t Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during the-month.

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. OPERATING DATA REPORT DCCKET NO. 50-327 DATE JULY 13, 1983 CCMPLETED SY F. G. EDDINGS TELEPHONE (615)370-6196 OPERATING STATUS

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

2.-REPORT PERIOD: JUNE 1 - JUNE 30 1983

3. LICENSED THERMAL POWER (MWT): 3411.0
4. NAMEPLATE RATING (GROSS MWE): 1220.6
5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
6. MAXIMUM DEPENDA5LE CAFACITY (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: Ige,m,6,-)gy,,

gross changed from 1163 to 1183 andrItem.70!DC net.-changed from ~ ~~~~

..bk_.b!__ aj{nX }j{el jj ,t,{e] {ry jj } yjj((n_cj ]e,s} { __ ,_ ,"

9. POWER LEVEL TO WHICH RESTRICTEDrIF ANY(NET MWE):... ____
10. EiI5555~iC5'55siliciiC55557' 555((((.~[_~~~_~.~[_~[~((~(((([~ _ _

THIS MONTH YR.-TC-DATE CUMULATIVE

11. HOURS IN REPORTING PEPIOD 720.00 4343.00 17520.C0
12. NUMBER OF HOURS REACTCR WAS CRITICAL 72C.00 3798.68 11334.38
13. REACTOR RESERVE SHUTDCWN HOURS 0.00 0.00 0.00 14 HOURS GENERATOR Oh-LINE 720.00 3715.70 11035.20
15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
16. GROSS THERMAL ENERGY GENERATED (MWH) 2441454.63 12107909.34 35390651.34
17. GROSS ELECTRICAL ENERGY GEN. (MWH) 837500.00 4173620.00 11931156.00
18. NET ELECTRICAL ENERGY GENERATED (V.WH) 809990.00 4023657.00 11459861.00
19. UNIT SERVICE FACTOR 100.00 85.56 62.99
20. UNIT AVAILABILITY FACTOR 1C0.00 85.56 62.99
21. UNIT CAPACITY FACTOR (USING MDC NET) 98.00 80.71 56.98-
22. UNIT CAPACITY FACTOR (USING DER NET) 98.00 80.71 56.98
23. UNIT FORCED OUTAGE RATE 0.00 4.20 13.69
24. SHUTDO.NS SCHEDULED OVER NEXT 6 MONTHS (TYPEr DATE, AND DURATION OF EACH):

_cys p_ _2_ m_q13a _o tsage. .te_b.gf3_n.e_csehr. Jh _19_a3_f o_r_ w a_ayn __ ________________

25. ii is5i55;s Ii is5 57 EEF5if- iii555 iiiisifi5 Bifi 57 iiiiiGFI-------

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

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET No. '50-327 UNIT one DATE June 1983 COMPLETED BY S. A. Lane TELEPHONE (615) 870-6196 MONTH JUNE, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1132 17 1127 2 1132 18 1129 3 1132 19 1131 4 1016 20 1130 5 1132 21 'I

'/.1.130 6 1133 22 1130 7 1132 23 1129 8 1131 24 1128 9 1134 25 1126 10 1133 26 1126 11 1131 27 1123 12 1132 28 1122 13 1131 29 1122 14 1131 30 1122 15 1128 31 16 1129 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)

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

UNIT NAME SEQUOYAH ONE DATE July 11, 1983 COMPLETED BY M. Eddings REPORT MONTH JUNE TELEPHONE (615) 870-6196 W

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- @g "'c c yt Licensee y Cause & Corrective No. Date 8, ty ~8 t2 Event 8 8% 8% Action.to R S$ @

C y* Report # M'8 8, '8 Prevent Recurrence E" $N$ N" 0" e

19. 810604 F A Power Reduction for Maintenance on Level Control Valve on #3 Htr Dr Tk.

h 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

. OPERATING DATA REPORT 00CKET NO. 50-328 DATE JULY 13, 1983 CCMPLETED BY D.C.DUPREE TELEPHONE (615)870-6543 OPERATING STATUS

1. UNIT NAME: SEQUOYAH NUCLEAR PLANTi UNIT 2 NOTES:
2. REPORT PERIOD: J UN E 1-30,19 33
3. LICENSED THERMAL POWER (MWT): 3411.0 4 NAMEFLATE RATING (GROSS MWE): 1220.6
5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1163.0
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1128.0
3. IF CHAhGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:_........ _.
9. POWER LEVEL TO WHICH FESTRICTEDrIF ANY(NET MWE):........
10. REASONS FCR RESTRICTIONSiIF ANY:__________________...._

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720.00 4343.00 9480.00
12. NUMBER OF HOURS REACTCR WAS CRITICAL 72C.00 4330.22 8213.92
13. REACTOR RESERVE SHUTDCWN HOURS 0.00 'O.00 0.00
14. HOURS GENERATOR Oh-LINE 720.00 4295.40 8102.15
15. UNIT RESERVE SHUTDOWN HOURS 786 eOSO 0.00 08, f40 0.00 188;3/o 0.00
16. GROSS THERMAL ENERGY GENERATED (MWH)l4 2216621.71 13985838.99 26140429.79
17. GROSS ELECTRICAL ENERGY GEN. (MWH) 7558050.00 16
18. NET ELECTRICAL ENERGY GENERATED (MWH) 7f5605.00 c50,460.00 020.00 $$P00310.00 8576310.60

, 19. UNIT SERVICE FACTOR 100.00 98.90 85.47

20. UNIT AVAILABILITY FACTOR 100.00 98.90 85.47
21. UNIT CAFACITY FACTOR (USING MDC NET) 89.71 94.92 80.20
22. UNIT CAPACITY FACTOR (USING DER NET) 82.15 93.27 78.80
23. UNIT FORCED OUTAGE RATE 0.00 1.10 9.19 1 24 SHUTD0wh5 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATER AND DURATION OF EACH):
P_f_u41WMiff. caste _ ggtam_ t939. _w=_t L L9_83_ rog a_ays . _ . ._ _ _ _ _ _ _ _ _ _ _ _

1 _....._... _ ___......... ________.......__..._____.____.__..._......

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

l ..._......_-_-___._ .__........_____ . ______...__.._..... ______

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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Two DATE June 1983 COMPLETED BY S. A. Lane TELEPHONE (615) 870-6593 MONTH JUNE, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) 1 1116 17 1117 2 1115 18 1115 3 1115 19 1115 4 1115 20 1116

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5 1113 21 -11115 6 1114 22 d!16' 7 1112 23 1116 8 1113 24 1115 9 685 25 1114 10 427 26 1113 11 456 27 1111 12 449 28 1111 13 629 29 1090 14 1032 30 1111 15 1111 31 16 1113 INSTRUCTIONS On this format, list the average daily unit power level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. ,

1 (9/77) l l

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

UNIT NAME- SEQUOYAH TWO DATE July 12, 1983 COMPLETED BY David Dupree REPORT MONTH JUNE TELEPHONE (615) 870-6543 w

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, gg " ,' c yy Licensee y Cause & Corrective

.>. Date 8, t8 8 yt2 Event g% 8% Action to y 2o @ 5y* Report ! "] 8.*g Prevent Recurrence 5" $N@ N" $"

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10. 830609 F 0 B 5 Add Oil to Number One Reactor Coolant Pump Motor a

5 I 2- 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling- 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License. Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source i

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

MECHANICAL MAINTENANCE

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1. Repaired pressure control valve 1-PCV-3-122.
2. Installed an adapter plate on 2BB boric acid transfer pump.
3. Tightened the Cam roller and adjusted the turnbuckles on the 734' airlock -

Unit 2.

4. Performed annual inspection SI-102 on diesel Generator IB-B.

, 5. Repaired and balanced the fan on the terry turbine room exhaust fan.

i 6. Replaced valve 2-63-603. Also installed spool piece and relief valve ,

with hanger on #2 accumulator on Unit 2.

7. Repaired one of two spare unlatching tools on the refueling floor.
8. Removed the stud and inspected the bearing and crank shaft on 2C Pd Pump.

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 the required repairs.
3. Checked and added oil to the Unit 2 RCP Motors.
4. Inspected and functional tested the refueling outage support equipment.
5. Completed repairs to intertie transformer Phase A.
6. Inspected and made repairs to start Bus IA.
7. Installed an oil purification system on the Auxiliary Building Chiller.
8. Replaced the Auxiliary Building Chiller package motor.
9. Replaced heat trace on the boric. acid pump supply line.
10. Repaired all underwater lights in the spent fuel pit and canal.
11. Started the 6 year inspection of the switch yard breakers (PCB's & MOD's).

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Plant Maintenance Summary (Continued)

Instrument Maintenance

1. Continued monthly calibration surveillance on Unit 1 & 2 UHI level switches.

A Barton engineer was contracted to inspect, repair, and calibrate all switches. He found several problems which were corrected. All switches on Unit 2 were found within the Tech Spec tolerance and 2 out of 4 switches on Unit 2 were found.within tolerance. All were repaired, recalibrated, and returned to service.

2. Completed installation of a flashing red light.on all area radiation monitors which can be passed without being below setpoint.
3. Fine tuned the instruments on the condensate demineralizer waste evaporator with operations during its initial run period. .

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4. Performed a recalibration to the Unit 2 Power Range Hi Flux trip setpoint to 55% due to Tech Spec action required for target band penalty time.
5. Containment sump level transmitter 1-LT-63-177 drifted above minimum acceptance criteria. Found capillary sense line had developed air bubble.

IM's evacuated sense line and topped off Tite system with oil and returned it to service.

Field Services Group

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

The installation of conduit and junction boxes on elevation 706 in the l auxiliary building was discontinued early in June and cable pulling has  !

begun for unit 1. Core drilling in the additional equipment building i

east outer wall is underway for HVAC duct installation. Prefabrication and installation of the HVAC duct serving the PASF area is continuing.

Installation of HVAC equipment se-wing both units is in progress in the PASF area as well. The instara't a of component cooling piping to the PASP coolers on unit 2 is -es:. n; ompletion except for the component ecoling piping tie-in to ch syr 0 which will require a unit outage.

Work is continuing to ins.-il tu;. 3 cst-accident sample tubing in the unit I room. Work is continuing to install the unit 2 post-accident sample tubing with work concentrating in the unit 2 PASF room as the

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majority of this work is complete in the annulus. Fabrication of the steel containment vessel penetration plates for the unit 2 post-accident sample tubing to the primary containment is delayed for material procurement. 'The demineralized water piping serving the unit 2 PASF equipment'is completely installed as insulation of this piping was completed this month.

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Plant Maintensnce Summary (Continued)

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

Installation of conduit and junction boxes in upper containment (excluding the ice condenser) is continuing. Installation of conduit hangers in the ice condenser in underway and will continue to be worked during a series of action statement periods during the current nonoutage period.

3. ENC 5009--ERCW Piping Changeout (Units 1 and 2)

Installation of piping for the unit 2 "A" train penetration room coolers is in progress and should be completed during July. Work is continuing during this reporting period to change out-the

hypochlorite piping serving both the units 1 and 2 containment spray heat exchanger ERCW piping.
4. ECN 5645--Steam Generator Blowdown (SGBD) 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 nearing completion for the unit I heat exchangers. Completion of this hanger work has been delayed because of the lack of sufficient hanger design and procurement of materials.

Work has begun to install instrumentation for the unit 1 SGBD and condensate systems. Fabrication and installation of piping, hangers, and flow elements on elevation 662 of unit 2 turbine building is t

continuing. The heat exchangers for unit 2 have been received onsite 4_

and their foundation pads have been installed. Fabrication and installation of the unit 2 condensate piping is continuing on elevation 685.

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5. ECN 5495--FSG Office Building Power Supply Installation of miscellaneous and communication cables for the building is continuing as manpower is available. Cable trays are being fabricated for installation in the turbine building but has been delayed due to lack of material.

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

Work is continuing to install conduit and cable outside the reactor building. The majority of the conduit that can be installed at this time is in place and the cable pulling is scheduled to be complete prior to the start of the unit 2 cycle 1 refueling outage in August.

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Plant Mzintenence Summary (Continued)

7. ECN 5237--Laundry Room Improvements All laundry equipment has now been placed in position. Installation of the drain serving equipment in the laundry facility was completed this month. Remaining work includes extensive modification of the laundry room ventilation system, masonry wall erection, completion of all conduit and power cables serving the facility, and installation of the laundry room chiller. Work has progressed this month on the

. laundry room ventilation, conduit, power cable, and chiller installation. i All work is scheduled to be discontinued in July because of the unit 2 cycle 1 refueling outage which is scheduled to start in August.

8. ECN 5596--Install Batch Neutralization Tank Piping and hanger installation is nearing completion in the turbine building but completion of the mechanical portion of this modification is currently delayed because of valve procurement. The mechanical work is scheduled to be completed in August of this year. Instrumentation and electrical work has not yet begun. The system is scheduled for interim operation by September 1, 1983.
9. ECN 5198--Technical Support Center (TSC)

The major work remaining in the TSC room is installation of the fire detection system arid computer term 2r;als. Work is continuing to install conduit at various elevations in the control building.

10. ECN 5642--Add N, Regulating Station To Supply N, To Deaeration Distribution System Inside Condensate Storage T3nks The nitrogen supply piping to the tanks is complete between the new liquid nitrogen supply station and the condensate storage tanks except for tie-in'at the tanks and installation of a valve that is being procurred at present. Conduit and cable installation is complete but termination of cables in valve cabinet No. 2 and at the pressure switches on the condensate storage tanks still remains to be worked.
11. ECN 2773--Install Radiation Detectors (Unit 2)

Installation of conduit and pulling of cable for the unit 2 reactor building ventilation radiation monitor was completed in June with the

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exception of tie-in to the not yet installed main control room panel

l. 2-M-30. Remaining work required to make this radiation monitor operable includes installation of-panels 2-M-30 and 2-M-31, cable pull into these panels, cable terminationsDat both the panels and'the field monitors, and internal panel wiring.

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Plant Maintentnce Summtry (Continued)

12. ECN 5582--Add N; Regulating Stations To Supply N To Steam Generators This system is charged 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 ECN 5642 portion

, of this report, the nitrogen piping tie-in for the unit 2 main steam piping, final modification of the valve cabinet covers, painting of the pipes, and insulation of the pipes remains to be completed.

13. ECN 5248--Nitrogen Truck Fill This work is to relocate the nitrogen truck fill pipes from the north to the east side of the auxiliary building. All new valve were installed and tie-in of the pipe extension to the existing piping was accomplished.

This ECN is now complete.

14. ECN 5519--Plant Crane Escape Devices 3

Structural members used to attached the escape devices to each polar crane in the reactor buildings were installed in June completing the structural work for this ECN. Sandblasting and painting of the members must wait until an outage.

15. ECN 5449--6.9-kV Shutdown Board Degraded Voltage Circuitry J

. Internal panel wiring is continuing for 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.

Termination of 28 cables routed between the above listed panels will be accomplished after the internal panel wiring is completed.

16. ECN 5867--Fuel Transfer System i

Because of insufficient design information, only the mechanical modification portion of the ECN was partially worked in June. Work was discontinued at the end of the month in order to prepare the refueling canal to receive the unit 2 new fuel.

17. L-DCR 1847--Chemical Feed Injection to Condensate Polisher Discharge

'All hangers have been installed and tubing installation is continuing for tie-in of the chemical feed system to'the condensate polisher discharge piping. This work is scheduled to be completed in July if the system tie-ins can be made.

18. L-DCR 1883--Liquid Nitrogen Station j Installation of the station equipment, piping, and electrical service is nearing completion. The high pressure portion of the nitrogen system is expected:to be operational by the-middle of July. The low pressure portion of the system lacks installation of a valve which is l being'procurred as already mentioned under ECN 5642 portion of L this report.

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Plant Maintentace Summary (Continued)

19. ECN 5050--Gaseous Effluent Radiation Monitoring The ventilation exhaust radiation monitor panel isolation valves have been installed during this reporting period for the units 1 and 2 shield building exhaust systems. This work completed ECN 5050.
20. ECN 5684--RCP Motor Oil Spray Shields-Work continued late in this reporting period to prefabricate the shields. This work is progressing smoothly and is expected to continue until the start of the unit 2 cycle 1 refueling outage.
21. ECN 5644--Hotwell Makeup and Dumpback Work was completed early in June to prefabricate and partially install a 5-inch piping assembly for the condensate storage tank "A". The section of piping in the pipe tunnel adjacent to the tank has been installed as much as possible at present. A unit outage period and {

coincident draining of the tank for tie-in of the piping as well.as )

tie-in of the piping to the condensate system during a unit outage 1 period is necessary to complete this ECN. Further nonoutage piping installation in the pipe tunnels adjacent to the CSTs "A" and "B" and in the turbine building still' remains to be completed as well.

22. ECN 5847--Plant Fire Dampers This ECN authorizes changeout or modification of several fire dampers located throughout the plant. Installation of the negator spring assemblies and post-modification testing of the dampers is continuing and is expected to be completed in August.
23. ' ECN 5399--Refueling Water Storage Tank (RWST) Platforms (Units 1 and 2)

Completion of platform installation and reposition of the ladder leading to the top of the unit 1 RWST was delayed this month because of material unavailability. The unit 2 work is underway as well.

24. L-DCR-1822--Condensate Sources To Secondary Chemical Feed System This work supplies two additional condensate sources to the secondary chemical feed system. Fabrication and installation of the 1-inch diameter piping is now complete except for final piping tie-in to the unit 2 gland seal water, the demineralized water, and the secondary chemical feed systems. These piping tie-ins will require system'catages.
25. L-DCR-1492--Turbogenerater Governor Valve Permanent Scaffolds (Units 1 and 2)

Fabrication and installation of permanent steel scaffolds above the turbogenerator governor valves for unit 2 is complete. This work is also complete for unit 1.

Plant Maintentnce Summary (Continued)

26. ECN 5026--PAX Telephone Extension To Auxiliary Building Roof Work was completed this month to install a PAX telephone on the auxiliary building roof.
27. ECN 5870--Auxiliary Building Drain To Turbine Building Sump
This ECN authorizes installing drainage piping with hose connections on each floor elevation in the auxiliary building which connects to existing piping that drains uncontaminated water to the turbine building sump. This work is underway as piping is being fabricated for installation.
28. L-DCR-1930--Secondary System Sample Sinks This DCR authorizes modifying existing sample sinks and associated piping for secondary systems that are located in the condensate demineralizer building to facilitate
29. L-DCR-1473-Secondary System Sample Sinks A vibration test was conducted on a portion of the unit 1 auxiliary feedwater suction piping serving the terry turbine steam driven pump and repair was made to pipe support 1-AF-200..

Miscellaneous Decontamination and storage of scaffolding used during the unit I cycle 1 refueling outage was completed in June. Outfitting of the temporary hot toolroom is continuing with a target date of July 5,1983 for removing all hot tools to the new location in the service building. Painting of the auxiliary building floors with protective coating is continuing and is scheduled to be completed by August 5, 1983, in time for the start of the unit 2 cycle 1 refueling outage. Painting of the auxiliary building equipment nametags is ongoing and will be discontinued August 5,1983, for the start of the unit 2 cycle 1 refueling outage. Work began this month to relocate the FSG insulator's trailer but progress has been delayed.because of equipment procurement.

Repair of fire barrier penetrations throughout the plant was continued throughout June only on an as needed basis as determined from SI-233 inspection. Work also began this month to install underwater lights in the reactor cavity.

17-

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--TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant

, P. O. Box 2000 Soddy-Daisy, Tennessee 37379 UUL 151983 Nuclear Regulatory Commission Office of Management Information-and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the June 1983 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY C. C.. Mason

[Y 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 101 Marietta Street. Washington, DC 20555 (2 copies)

Suite 3100 Atlanta, GA 30303 (1 copy) INPO Records Center

.' Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, GA 30339 (1 copy)

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)

ZE14

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