ML20062F918

Monthly Operating Repts for June 1982

ML20062F918
Person / Time
Site:	Sequoyah
Issue date:	07/12/1982
From:	Dupree D, Eddings M TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20062F916	List: ML20062F914 ML20062F918
References
NUDOCS 8208120202
Download: ML20062F918 (23)

Text

r TENNESSEE VALLEY AUTIIORITY DIVISION OF NUCLEAR POWER SEQUOYAll NUCLEAR PLANT MONTifLY OPERATING REPORT JUNE 1, 1982 - JUNE 30, 1982 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l

Submitted By: .

, WPower Plant Superintendent l

l l

l i

820812O202 820630 l PDR ADOCK 05000327 1 R PDR

. l TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . . 1-8 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . . 8 Licensee Events and Special Reports . . . . . . . . . . . . . . . . . . 8-10 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . . . . . . 10 Operating Data Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11-13 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-16 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . . 17 Field Services Maintena.,ce Summary . . . . . . . . . . . . . . . . . . . 17-18 Appendix A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19-21

Operations Summary June, 1982 The following summary describes the significant operational activities j 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 693.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, produced 754,850 MWH (gross) with 3.61 percent station service use resulting in an average hourly gross load of 1,092,007 KW during the month. The net heat rate for the month was 10,790 BTU /KWH. There are 64.85 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 September 14, 1982. The capacity factor for the month was 89.6 percent.

, There were no reactor scrams, one manual shutdown, and six power re-ductions during June.

Unit 2 1

Unit 2 was critical for 697.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, produced 646,410 MWH (gross) with 4.08 percent station service use, resulting in an average hourly gross load of 980,970 kW during the month. The net heat rate for the month was 10,610 BTU /KWH. There are 306.9 full power days estimated remaining until the end i

of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached June 27, 1983. The capacity factor for the month was 75.9 percent.

l There were five reactor scrams, no manual shutdown, and nine power reductions during June.

Significant Operational Events Unit 1 Date Time Event 06/01/82 0001 Reactor in mode 1 at 100% power, pro-ducing 1150 MWe.

06/03/82 1141 Dropped load 2% for SI-139, Determina-tion of the AT Power Moderator Tempera-ture Coefficient.

1152 Increased reactor power back to 100%

after SI-139 was completed.

1

Significant Operational Events (Continued)

Unit I Date Time Event 06/12/82 0630 Reactor at 100% power, producing 1150 MWe. Began decreasing power to per-form SI-90.3, Reactor Trip Instrumenta-tion Monthly Function Test (Racks 5 and 6). (Loop 2 Tavg AT out of service during this SI.)

1425 Reactor power 97%.

1520 Began power ascension.

1 Reactor at 100% power, producing 1150 1605 MWe.

2220 Reactor at 100% power, producing 1140 MWe. Valve position limiter holding the MW's down. The limiter would not respond to an increase signal.

06/13/82 0620 Reactor at 98% power and the turbine valves are on valve position limiter.

j 1028 Reduced load for maintenance on the EHC rate comparator.

1200 EHC rate comparator repairs completed.

Began power ascension.

2 1425 Reactor at 100% power, producing 1150 MWe.

06/15/82 1240 Reactor at 100% power,1150 MWe. Began

, load reduction to change the EHC rate comparator card for governor valve - 2.

1310 Reactor at 92% power, EHC card replaced, began power ascension.

1455 Reactor at 100% power, producing 1150 MWe.

06/21/82 0657 Reactor at 100%, producig 1150 MWe.

Began reducing power to stop the Hi steam flow bistable blips so SI-90.5, Reactor Trip Instrumentation l Monthly Function Test (Racks 9 and 10),

could be performed.

Significant Operational Events (Continued)

Unit 1 Date Time Event 06/21/82 0725 Reactor at 98% power.

0920 Began power ascension.

2225 Reactor at 100% power.

06/26/82 1058 Began load reduction at 1% per minute to take the unit off line to repair a leak on the #2 main steam check valve.

1216 Turbine off-line.

1300 Reactor entered mode 3.

2355 No. 2 main steam check valve repairs complete.

06/27/82 1526 Reactor taken critical.

1701 Tied on-line.

2220 Reactor at 30% power.

06/28/82 0007 No. 7A heater drain tank pump stopped for inspection due to bearing problems.

1530 Reactor at 65% power, producing 745 ffWe and holding. Repairs continued on #7A heater drain tank pump.

06/29/82 0117 Began power ascension.

1 0540 Reactor at 90% power and holding.

Waiting for #7 heater drain tank pump

, to be returned to service.

06/30/82 0704 No. 7A heater drain tank pump back in service.

1255 Began power ascension.

2359 Reactor in mode 1 at 98% power.

Significant Operational Events (Continued)

Unit 2 Date Time Event 06/01/82 0001 Reactor in mode 2 at 1% power.

1320 Reactor entered mode 1.

1443 Turbine tied on-line, increased power to 30% and held for secondary chemistry to come into specification.

06/02/82 1006 Began power ascension.

1300 lloiding reactor at 39% power, 393 MWe, due to problems with the MFPT governor valves.

1613 Began power ascension.

06/03/82 0625 Reactor at 97% power, 1122 MWe.

2142 Performed Start-Up Test 9.3, 50%

load rejection.

2149 Began increasing power back to 100%.

06/05/82 0625 Reactor at 98%, 1160 MWe.

06/07/82 0616 Reduced load to reset the over-power delta T setpoints.

0735 Reactor at 95% power, 1120 MVe.

0845 Began power ascension.

0911 Reactor at 100% power, 1155 MWe.

06/08/82 0630 Began load reduction to reset the overpower delta T setpoints.

l 0715 Reactor at 95% power, 1110 MWe.

. 2146 Began power ascension.

2220 Reactor at 96% power, 1110 MWe.

06/09/82 0630 Reactor at 100% power, 1150 MWe.

l l 2200 Began load reduction to work on the l discharge valve on MFPT A.

l l l a

Significant Operational Events (Continued)

Unit 2 Date Time Event 06/10/82 0235 Reactor at 48% power, 520 MWe A-MFPT off-line for repairs on the discharge valve.

1243 Began power ascension.

1310 Reactor at 50.5% power, 559 MWe A-MFPT discharge valve maintenance continues.

06/11/82 0104 Began power ascension.

0430 Reactor at 95% power, 1120 MWe and holding for calibration of the over-pcwer delta T setpoints on loop 3.

06/12/82 1330 Began power ascension.

2115 Reactor at 100%, 1156 MWe.

06/13/82 1238 Began power reduction to add oil to reactor coolant pump #1.

1608 Reactor at 4% power, turbine off-line.

2340 Reactor entered mode 1.

06/14/82 0040 Turbine on-line. Increasing to 30%

power and hold waiting for secondary chemistry to come into specification.

0950 Began power ascension.

1050 Reactor at 38% power, 379 MWe and holding while placing the MSR's in s e rvice .

1 1300 Began power ascension.

06/15/82 0045 Reactor at 100% Power,1152 MWe.

06/16/82 1220 Reduced load to re-evaluate the AT power level indicators.

1420 Reactor at 97% power, 1140 MWe.

2200 Reactor at 100% power,1149 MWe.

s

i 4

Significant Operational Events (Continued) l Unit 2~

l  ;

1 l

! Date Time Event l 06/18/82 2200 Began a load reduction for maintenance on B-MFPT orifices. One orifice was loose. The other was dirty.

2320 Reactor at 60% power - B-MFPT off-line.

06/19/82 0450 Began power ascension.

i 1 0625 Reactor at 90% power, 1015 MWe and l holding for SI-78, Power Range Neutron Flux Channel Calibration by Heat Balance Comparison.

0744 SI-78 completed, began power ascension.

1429 Reactor at 100% power.

06/24/82 1514 Received a Lo level alarm on #1 steam I generator. The feedwater reg. valve was wide open, opened the bypass valve wide open, and was eble to maintain the steam generator levels.

1516 The level in #1 steam generator began dropping, started reducing load.

1518 Reactor tripped due to Lo-Lo level in

1. 1 steam generator due to the feed-

water reg. valve drifting.

i 2050 Reactor taken critical.

.1 1 2140 The reactor entered mode 1.

2152 Reactor tripped due to steam flow /

feedwater flow mismatch during start-up.

, 06/25/82 0315 Reactor taken critical.

0338 Reactor tripped due to steam flow /

feedwater flow mismatch during start-up.

0535 Reactor taken critical.

0750 Reactor tripped due to Lo-Lo steam  ;

e generator levels when PCV-3-122

failed closed.

[

Significant Operational Events (Continued)

Unit 2 Date Time Event 06/25/82 1533 Reactor taken critical.

1615 Reactor entered mode 1.

1730 Tied on line.

1840 The reactor exceeded its AI band for more than 60 minutes, therefore, reactor power must be maintained at

<50%. Reactor holding at 30% for secondary chemistry to come into specifications.

06/26/82 1018 Began power ascension.

1600 Reactor at 64% power, 743 MWe and holding for repairs on a drain valve on #3C heater drain tank pump.

1931 Began power ascension.

06/27/82 0200 Reactor at 92% power and holding while a leaking flange on Al-MSR was repaired.

06/28/82 0645 Reducing load to repair a leak on valve 3-510.

1810 Reactor at 20% power, 177 MWe.

2240 Reactor at 25% power, 146 MWe.

Reducing turbine load while main-taining reactor power for repairs on valves 3-510.

2303 Turbine off-line, reactor power 25%.

06/29/82 0505 Repairs completed on valve 3-510.

0645 Tied on-line.

0803 A Hi level alarm in #3 steam generator tripped the feedwater pumps and main turbine.

I Significant Operational Events (Continued)

Unit 2 Date Time Event 06/29/82 0807 The MFPT's were in manual and the valves came wide open. When the operator raised the speed of the feedwater pump, they could not catch the steam generator levels. The reactor tripped on a Lo-Lo #4 steam generator level.

1010 Reactor taken critical.

1110 Reactor entered mode 1.

1157 Unit tied on line, increased to 30%

power and holding for secondary chemistry to come into specifications.

1920 Began power a scension.

06/30/82 1420 Reactor at 99% power, 1140 MWe.

2359 Reactor in mode 1 at 99% power pro-ducing 1140 MWe.

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

Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during June 1982, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

Unit 1 LER SUBJECT SQRO-50-327/82059 Excore neutron instrumentation power range channel (N-42) lost power due to failure of high voltage supply 1-PX-92-5006B.

SQR0-50-327/82065 One ice condenser intermediate deck door (bay 3, door #4) was frozen closed due to a leaking air handling unit drain line. The leak was caused by a failed flange gasket.

i

! Licensee Events and Special Reports I Unit 1 (Continued)

LER SUBJECT i

i SQRO-50-327/82066 Steam generator blowdown containment isolation 1 valves 1-FCV-1-14 and 1-FCV-1-25 failed to close due to ruptured diaphragms. The ruptured

. diaphragms were caused by high temperatures.

1

! SQRO-50-327/82067 Diesel generator IB-B was inoperable when the 120V control power fuses blew when a burned

out bulb was being replaced. The bulb shattered j and shorted the filaments.

1 SQRO-50-327/82068 Condenser vacuum exhaust rad monitor 1-RM-90-119 indicated spurious high radiation signals due to noise. ,

SQRO-50-327/82070 Containment sump level instrumentation loops have the possibility of being inoperable during a LOCA due to sealed water legs flashing to steam.

! SQRO-50-327/82071 Control room emergency ventilation Train A failed to meet the minimum flow rate during the performance of SI-144.2. Vibration partially closed off the manual suction dampers supplying the emergency air clean-up fans.

! SQRO-50-327/82072 Boron injection tank heat trace circuits 113P and 119S had bad controllers. Circuit 117S had a bad thermocouple.

Unit 2 SQRO-50-328/82060 Lower containment airlock door would not close due to broken cam follower bearing.

SQR0-50-328/82061 Train A ABGTS was inoperable due to a pneumatic jumper being inadvertently lef t installed following maintenance on damper 2-FCO-30-271.

The jumber bypassed the controlled solenoid.

SQRO-50-328/82063 Ice condenser flow passages were blocked by excessive frost and ice due to an air handling unit drain line being blocked by sand blast pellets causing the pan to spill over.

,, - , . - - - r-nv-,--w r .-m- - , , - -

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Licensee Events and Special Reports Unit 2 (Continued)

LER SUBJECT SQR0-50-328/82064 Lower containment airlock failed air leak rate test SI-159.1 due to air leakage through the handwheel shaft packing.

SQRO-50-328/82069 2-FCV-43-2 and 2-FCV-43-11 pressurizer sampling containment isolation valves would not open because the valve operator air supply regulators were set 20 psi under required values.

SQRO-50-328/82073 Steam generator #4 blowdown isolation valve 2-FCV-132 would not stay open due to a limit switch out of adjustment.

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

Offsite Dose Calculation Manual Changes Changes in the Sequoyah Nuclear Plant ODCM are described in this section in accodance with Sequoyah Technical Specification 6.14.2.

These changes were officially approved by RARC on April 29, 1982. See Appendix A at the end of this report of these approved ODCM page changes.

OPERATING DATA REPORT DOCKET NO. 50-327 July 1, 1982 DATE COMPLETED BY M. Eddings TELEPHONE (615', 751-0343 OPERATING STATUS

1. Unit Name: Sequoyah One Notes

2. Reporting Period: June 1982

3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross MWe): 1220.58

5. Design Electrical Rating (Net MWe): 1148

6. Maximum Dependable Capacity (Gross MWe): 1163

7. Maximum Dependable Capacity (Net MWe): 1128

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 4,343 8,760

12. Number of Hours Reactor Was Critical 693./ 3,001./ 3,su3 -~~

-~

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 691.3 2,897.3 5,587.65

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2,292,528 9,332,182 17,397,136

17. Gross Electrical Energy Generated (MWH) 754,850 3,140,240 5,786,190

18. Net Electrical Energy Generated (MWH) 727,594 3,005,150 5,532,174

19. Unit Service Factor 96.0 66.7 63.8

20. Unit Availability Factor 96.0 66.7 63.8

21. Unit Capacity Factor (Using MDC Net) 89.6 61.3 56.0

22. Unit Capacity Factor (Using DER Net) 88.0 60.3 55.0

23. Unit Forced Outage Rate 4.0 33.3 22.1

24. Date and Shutdowns Scheduled Over Next 6 Months (Type (Schedu, led) Duration of Each):

Refueling / Modification Outage September 14 6 Months

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY 8-zi-60 /-zz-no COMMERCIAL OPERATION 7-1-81'~~ 7-1-81 (9/77) i UNIT SHUTDOWNS AND POUER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Seonovah one DATE J u 4' 7 , IW COMPLETED BY M. Eddines REPORT MONTH June TELEPHONE (613) 751-0343 m

u .,

wo* o e* =^ " ou3 'I *""

• a En Cause & Corrective

~,c S$ @ y5g Event 3.g gg Action to R y8 8 ,8 3 y Report # (e gg Prevent Recurrence a

Y5 N $5 zm9 O

8 3 82/06/26 F 28.7 A 1 Steam Leak on #2 Main Steam Check Valve 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 l .

r AVERAGE DAIL7 UNIT POWER LEVEL DOCKET NO. 50-327 UNIT Sequoyah one DATE .luly 2, 1982 COMPLE1ED BY M. Eddinns TELEPif0NE (615) 751-0343 MONTl! June, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1,111.5 17 1,103.8 2 1,111.5 18 1,104.2 3 1,110.2 19 1.099.9 4 1,111.0 20 1,103.5 5 1,113.0 21 1,097.0 6 1,111.3 22 1,103.3 7 1,110.5 23 1,102.5 8 1,112.5 24 1,102.5 9 1,113.5 25 1,101.7 10 1,111.5 26 534.7 11 1,111.2 27 67.7 12 1,095.0 28 500.3 13 1,096.8 29 965.8 14 1,104.2 30 1,049.3 15 1,105.8 31 N/A 16 1,106.3 INSTRUCTIONS On this format, list the rage daily unit power level in MWe-Net for each day in the reporting month. Compate to the nearest whole megawatt.

(9/77)

I" OPERATING DATA REPORT

! DOCKET NO. 50-328 DATE July 1, 1982 <

i COMPLETED BY David Dupree TELEPHONE (615) 751-0343 j

OPERATING STATUS

1. Unit Name: Sequoyah Two Notes i 2. Reporting Period: June 1982 1 3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross MWe): 1220.58

5. Design Electrical Rating (Net MWe): 1146

6. Maximum Dependable Capacity (Gross MWe): 1183

7. Maximum Dependable Capacity (Net MWe): 1148

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons

l

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 720 720 i '

by/.3

12. Number of Hours Reactor Was Critical 69/.3 09/.3

13. Reactor Reserve Shutdown Hours u o o

14. Hours Generator On-Line 658.95 658.95 658.95

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,918,281.3 1,918,281.3 1,918,281.3

17. Gross Electrical Energy Generated (MWH) 646,410 646,410 646,410

18. Net Electrical Energy Generated (MWH) 620,042 620,042 620,042

19. Unit Service Factor 91.5 91.5 91.5

20. Unit Availability Factor 91.5 91.5 91.5

! 21. Unit Capacity Factor (Using MDC Net) 75.0 75.0 75.0

22. Unit Capacity Factor (Using DER Net) 75.0 75.0 75.0 i 23. Unit Forced Outage Rate 8.5 8.5 8.5 l 24. Shutdowns Scheduled Ice Weighing 11-4-82 Over Next 6 Months per Technical Spec (T cations ge, Date, and Duration of Each):

I 25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 11-5-81 11-5-81 ,

INITIAL ELECTRICITY 12-31-81 12-31-81 COMMERCIAL OPERATION 6-1-82 6-1-82 i

(9/77)

UNIT SHUTDOWNS AND PO*ER REDUCTIONS DOCFET NO. 50-328 UNIT NAME Sequovah Two DATE July 6, 1954 COMPLETED BY David Dupree REPORT MONTH .iune TELEPHONE (615) 751-0343 m

u u N* ^" C C 3 Li nsee g, gn Cause & Corrective o 3 '0' "5 e 5" g Event 3 (j g 4; Action to R

y5 M ,8 g & Report # gg g.f Prevent Recurrence YD o N NE~

r. m 5 O

c 1 82/06/01 S 14.7 B 4 Start-Up Test 9.4A, 100% turbine trip.

I 82/06/04 S 0 B 5 Start-Up Test 9.3, 50% load rejection.

2 82/06/10 F 0 A 5 Maintenance "A" MFPT discharge valve. Reduct 1 load.

i 2 82/06/13 F 8.5 A 5 Reduce reactor load to 2%. Add oil to #1

( RCP. Reduce load, v

3 82/06/24 F 26.2 A 3 Reactor Trig Lo-Lo #1 S/G 1evel. Regulator valve drifted closed causing feedwater isolation.

4 :82/06/28 F 7.7 A 5 Dropped load to repair valve 3-510. Reactor 9 25%.

5 82/06/29 F 3.9 G 3 Reactor tripped Lo-Lo level #4 S/G after Hi-Hi level tripped the turbine, i

1 2 3 4 l F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual 5 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

S AVERAGE DAILY UNIT POWER LEVEL i

i DOCKET NO. 50-328 l UNIT Sequoyah Two DATE July 1, 1982 COMPLETED BY David Dupree TELEP110NE (615) 751-0343 MONTl! June 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Fet) (MWe-Net) 1 71.3 17 1,057.3 2 380.0 18 1,106.7 3 1,062.0 19 999.8 4 1,120.2 20 1,113.7 5 1,112.0 21 1,113.2 6 1,113.2 22 1,113.5 7 1,107.8 23 1,112.7 8 1,112.2 24 710.5 9 1,111.3 25 68.0 10 551.5 26 515.3 11 939.5 27 998.5 l 12 1.091.2 28 529.9 l 13 689.5 29 158.2 14 502.2 30 1,023.5 15 1,112.7 31 NA 16 1,117.0 1

INSTRUCTIONS l

l 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)

I . .

2 Plant Maintenance Summary 1

The following significant maintenance items were completed during the 4 month of June 1982:

Mechanical Maintenance

1. The Furmanite vendor stopped leaks on valves 2-3-67 and 2-3-81 on the MFPT's.

. 2. Replaced the diaphragms in the steam generator blowdown valves 1-1-7, l 1-1-14, and 1-1-25.

i Electrical Maintenance 1

1. Added oil to the Unit 2 reactor coolant pump motors.

l 2. Started repairs on the spare reactor coolant pump.

i Instrument Maintenance During the month, the containment sump level channels of Unit 1 and Unit 2 were declared inoperable because of potential failure of the water filled

, sensor systems of the transmitters. The water filled systems were refilled with silicone oil, and the channels returned to normal on July 2, 1982.

Westinghouse Nuclear Service Division representatives were on site to direct the filling operation. The plant operated under a temporary change to the Sequoyah Technical Specifications during the 15 days the channels were out of service.

Field Services Maintenance Work continues on the following items:

1. The indicating bellows, housings, level transmitters, and sensing lines have been changed out on all of the containment sump level transmitters.

Oil has been installed as the sensing fluid and the transmitters have been re-calibrated. The old bellows and sensing lines inside the crane wall will be removed when time permits.

. 2. Cable pulling, the installation of panel 1-M-30 and cable termination is all that remains to be done for the installation of the post accident area radiation monitors and containment isolation radiation monitors.

i

3. The diesel generator 1A-A batteries and racks were changed out. 2A-A

) batteries and racks remain to be changed out.

4. Cable pulling from the auxiliary control room to the fif th diesel generator is underway.

5. IE Bulletin 79-14 hanger inspection and modifications continues.

Field Services Maintenance (Continued)

6. A post indicator is being installed on 0-VLV-26-857 which supplies fire protection to the central alarm station (CAS).

7. Piping installation continues on the post accident sampling system.

8. The change out of carbon steel piping to stainless steel piping continues on several coolers supplied by ERCW.

The following work was completed during the month.

1. Door A-133 has been changed out and a card reader installed.

2. The radiation monitor flow switches have been replaced in the Unit I radiation monitors.

..= __ -.

APPENDIX A Change 1 Description of Change A small number of typographical corrections to the ODCM were approved as follows:

i l (1) Several radionuclides inadvertently left out during previous i revision work and added to table 2.1 as shown on the attached j table; these are inserted between NB-97 and RM-103.

(2) On table 2.1, TC-129 is changed to TE-129.

(3) On table 1.1, Ym-91 is changed to read Y-91m.

l (4) On table 1.5, the readings for the second and last columns are l designated DFY2 and DFB2 respectively.

Analysis on Evaluation Justifying Change These changes incorporate typographical corrections only.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations No effect.

Change 2 i

Description of Change The environmental monitoring section of the ODCM is changed as follows:

(1) The sampling and collection frequency for the third entry under pathway 3.C is changed to read:

Grab sample once per 31 days from Little Soddy Creek. Sample at TRM 503.8 collected by auto-matic sequential-type sampler with composite sample collected over a period of 5 31 days.

(2) On table 3.1-2, the following monitoring locations are added:-

(a) Fa rm EM at 2 Miles N (b) Farm BR at 2k Miles SSW (c) Farm G at 1 Miles NNW (3) Figure 3.1-4 is modified to indicate an automatic water sampler at TRM 503.8.

r APPENDIX A Change 2 (Continued)

Analysis or Evaluation Justifying Change Changes (1) and (3) are made as a result of the commitment in the Watts Bar Nuclear Plant (WBN) monitoring program to install an automatic water sampler on the first potable water supply downstream from WBN. This station is also the upstream station for the Sequoyah drinking water monitoring program.

Change (2) is made as a result of evaluations of land use performed in accordance with SQN Technical Specification 3/4.12.2.

Evaluation of Accuracy of Dose Calculations or Setpoint Determinations No effect.

Change 3 Description of Change Section 2.3.2 of the ODCM is revised to provide a new list of principal

isotopes for dose evaluations on releases to water systems as follows

Old List New List H-3 H-3 P-32 P-32 Mn-54 Mn-54

• Fe-55 Co-58 l Co-58 Co-60 I

Co-60 Sr-90

• Sr-89 Nb-95 Sr-90 Xe-133 Nb-95 **Cs-134 Xe-133 **Cs-136

• Ce-144 **Cs-137

• Deleted ** Added Analysis on Evaluation Justifying Change The changes permit more accurate estimate of the monthly dose from effluent releases. Change resulted from the annual check delineated in section 2.3.2.2 of the ODCM.

Evaluation of Accuracy of Dose Calculations on Setpoint Determinations The dose calculations will provide better estimates of monthly dose calculations for radiological effluent technical specifications compliance.

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