ML20093E755
| ML20093E755 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1984 |
| From: | Dupree D, Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8410120243 | |
| Download: ML20093E755 (40) | |
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s TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR P0tER SEQUOYAH NUCLEAR PLANT
,, MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION AUGUST 1, 1984 - AUGUST- 31, 1984 J
UNIT 1 DOCKET NUMBER 50-327 LICENSK NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79
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Submitted By: - -
Plant Manager l
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8410120243 840831 DR ADOCK 05000 { pk j
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TABLE OF CONTENTS a
Operations Summary . . . . . . . . . . . . .. . . . . . . . .1 Significant Operational Events . . .. . . .. . . . . . . . . . 3 PORV's and Safety Valves Summary . . . . . .. . . . . . . . . .3 Reports Licensee Events . . . . . .. . .. . . . . . . . . . . . . 3-6 Diesel. Generator Failure Reports . . . . . . . . . . . . . '6 iSpecial Reports . . . . . .. . . . . .. . . . . . . . . .6 Offsite Dose Calculation' Manual Changes . . .. .. .. . . . .6 Operating Data a
Unit 1 . . . . . . . . . . . . . . . .. . . . . . , . . , 7_9 Unit 2 . . . . . . . . . . . . . . .... . . . . . . . 10-12 Plant Maintenance Summary . . . . .. . . . . . . . . . . . . 13-26 Appendix A . . . . . . . . . . . . .. . . . . . .. . . . . . 27-37 s %
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. . Operations Summary August, 1984 1
The.following summary describes the significant operational activities for the month of August. In support of this summary, a '
chronological log of significant events is included in this report.
Unit 1 Unit I was critical for 718.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, produced 746,040 MWH (gross),
resulting in an average hourly gross load of 1,063,872 kW during the month.
There are 283.8 full power days estimated remaining until the end of cycle 3 fuel. With a capacity factor of 85 percent, the target EOC expcsure would be reached July 31, 1985. The capacity factor for the month was 84.8 percent.
There was one reactor scram, and no manual shutdowns, or power reductions 1during the month.
Unit 2 Unit 2 was critical for 514.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, produced 538,060 MWH (gross),
resulting in an average hourly gross load of 1,083,597 kW during the month. There are 6 full power days estimated remaining until the end of cycle 2 fuel. The cycle 2 refueling outage is scheduled to begin on September 21, 1984'. The capacity factor for the month was 61.1 percent.
There was one reactor scram, one manual shutdown, no power reductions during the month.
Significant Operational Events Unit 1 Date Time Event 08/01/84 0001 The reactor was in mode 1 at 100%
power producing 1118 MWe. An investigation was underway to determine the lost generation.
08/27/84 2033 The reactor tripped following a steam flow /feedwater flow mismatch in loop 1 when the feedwater regulation valve failed closed.
08/28/84 2158 The reactor was taken critical.
08/29/84 1518 The turbine was tied on-line.
, 1825 The reactor obtained 30% power and held due to steam generator chemistry.
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. . Significant Operational Events Unit 1-(Continued)
Date Time Event 4
08/30/84 1339- Began power ascension.
08/31/84 0518 The reactor was' holding' at 84% power while starting a #3 HDTP.
0536 Resumed the power ascension.
1400 The reactor obtained 99% power.
2359 The reactor was in mode - 1 at 99%-
power producing 1088 MWe. The-investigation continues to determine the lost generation.
Unit 2 Date Time Event 08/01/84' 0001 The reactor was in mode 1 at 100%
power producing 1140 MWe.
08/20/84 1151 Began a manual shutdown due.to a leaking pressurizer relief valve and failed rupture disk on the pressurizer relief tank.
4 1337 The unit was taken off line.
1356 The reactor entered mode 3.
I 2035 The reactor entered mode 4.
08/21/84 1150 The reactor entered mode 5.
08/26/84 1713 The reactor entered mode 4.
. 08/27/84 1302 The reactor entered mode 3.
08/29/84 1944 The reactor was-taken critical.
2136 The reactor was in mode 2 at 4%
power and holding due to chemistry.
- . 08/30/84 0450 The reactor entered mode 1.
0825 Tied the unit on line.
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1- .' Significsnt Opsrational Events
's Unit 2' j l
(Continued) 1 l
Date Time Event
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08/30/84 .0843 The turbine tripped due a Hi-Hi
- 1 steam generator level-followed by-a' reactor trip due to a.Lo-Lo #3 steam generator level.
1741 The reactor was taken critical.
2122 -Tied the unit on line.
08/31/84 0319 The reactor obtained 30% power and was holding steam generator chemistry to come into specification.
2359 The reactor was in mode 1 at 30%
power producing 288 MWe and was
- still holding due to steam generator chemistry.
PORV'S and Safety Valves' Summary No PORV's or safety. valves were challenged during the month.
i Licensee Events and Special Reports
! The following Licensee Event Reports (LER's) were sent during August 1984, to the Nuclear Regulatory Commission.
LER DESCRIPTION OF EVENT j
1-84044 On July'5, 1984 with unit 1 and 2 in mode 1 at.100% power,.
during the performance of SI-7, " Electrical Power Systems:
Diesel Generators", the IA-A diesel generator was started by a safety injection actuation start signal as required a
by the test. The 43T (L) switcb was returned to the normal position from the test position prior to- resetting of the' safety injection signal. This condition resulted in automatic start of the remaining three (3) diesel generators.
1-84045 On June 25,_1984, unit I and 2 in mode I at 100% power, the A-A auxiliary control air. compressor was taken out of service for maintenance. Due to insufficient spare parts, it was not returned to service. On July 9, 1984, at 0750
- CST, the B-B auxiliary control air compressor was removed
- from service. These compressors are not technical specifi-l cation equipment, but are attendant equipment for various '
j safety systems (auxiliary feedwater being the most limiting l with respect to action times). With both trains inoperable,.
it was determined that entry into 3.0.3 should be made, and
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- . . Licensee Events and'Special Reports l (Continued)~
LER- DESCRIPTION OF EVENT 1-84045~ 3.0.3 was entered at 0750 CST on July 9,1984. Power reduction.to mode 3 was initiated but was stopped at 88% ,
when the BB compressor was returned to service. '
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1-84046 Following an inspection of various. safety-related systems at Sequoyah, interactions were found that were not in
- compliance with Appendix R of 10'CFR 50. Fire watches have been-established.as required per action statement of Technical Specification 3.7.12 and will continue until compliance with Appendix R can be made. This report is
. required per license condition 2.H, 10.CFR 50.73 (a)(2)(ii) and special report requirements. of Technical Specification
. - 3.7.12. . Interactions were found that involved power feeds-from the 6900V shutdown board to the :480V shutdown trans-4 formers, redundant divisions of ERCW pump, fire pump, component cooling water pumps, auxiliary feedwater pumps and pressurizer r heaters.
1-84047 The auxiliary building (ABI) :and containment building (CVI) isolations occurred at 0/20 on July 17, 1984 while unit I was in mode 1 at 100% power.
, Maintenance personnel were troubleshooting the check source i '
circuit on radiation monitor RM-90-141 when the check source wire slipped loose and fell against the 120 VAC input for RM-90-134 power supply. ' This caused breaker 12 on the 120 VAC vital instrument power board 1-II to trip. The resulting loss of power, trainB', to the ratemeters on RM-90-112, RM-90-103, and RM-90-134 and RM-90-140 caused i an ABI and a CVI. The ratemeters fail in the safe.(trip) condition upon loss of power. The breaker, the radiation monitors, and the ABI and CVI logic were all reset and returned to service. No parts were replaced, and the check source circuit was repaired.
1-84048 During a review of instrumentation drawings, it was discovered that a reactor coolant coolant system (RCS) pressure channel did not presently exist in the field. Only one pressure i- channel, scaled 0-600 psig, was installed and operable. This
! 0-600 psig channel was rescaled to 0-3000 psig and placed in j service.to meet the two channel requirement. The 0-600 psig l- indicator is not required.
t I A design' change had been made the last refueling outage which l moved the required channels. The existing channel indicator l and a recorder were considered to fill the two channel requirement. After investigation, it was determined that the indicator and recorder were fed from the same transmitter.and one indicator was scaled wrong, thus not providing two independent wide range indications. The rescaled channel will provide redundant pressure indication until the other indicator can be' rewired.
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. ., Licentce Evnnts'and Sptcial Reports ,
(Continued).
LER DESCRIPTION OF EVENT 1-84049 Following. additional inspections of various safety-related systems at Sequoyah, interactions were found that were not in compliance _with Appendix R of 10 CFR50. Fire watches have.been established as required per action statement of Technical Specification 3.7.12 and_will continue until compliance with Appendix R can be'made. This report is required ~per license condition 2.H, 10 CFR 50.73 (a)(2)(ii) and special report requirements Technical Specification 3.7.12.
Interactions exist between:
A. Train A and train B at elevation 749, in the 1A 480V transformer room.
B. Train A and train B at elevation 749 in the 2B 480V
- transformer room.
C. Train A and train B at elevation 759.0 in the unit 1
, control rod equipment room.
D. Train A-and train B at elevation 759.0 of.the unit 2 control rod drive equipment room.
! E. Cables.at elevation 749 in the 480 V reactor MOV board room 2A.
i 2-84011 This LER involves three separate incidents. The first a contalument ventilation isolation (CVI) occurred at 0124C on July 13, 1984, while unit 2 was in mode.1 at 100%.
I power. The second CVI occurred at 0744C on July 14, 1984, while unit 2 was in mode 1 at 100% power. Third CVI occurred at 0158C on July 15, 1984, while unit 2 was in mode 1 at 100% power. The operator responded to the alarm (RM-90-112 for all three incidents) and determined that the alarm was in fact caused by a spurious spike and not by a
, high radiation level. Maintenance personnel were notified i
to check the monitor, reset the alarm in the control room, j and repair or reset the monitor.
In the first incident, an EMI spike was generated when the low flow switch was actuated due to the filter paper running out. No failure was found associated with the monitor and it was reset. Instrumentation is adding a time delay to the i 7 actuation signal to allow time for the spike to decay and l prevent spurious CVI initiation.
! In the second and third incidents, an EMI spike occurred due to an unknown source. The transient was too short to be recorded.
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.$' - Liczntre Ev nta and Sp2cial' Reports (Continued)
LER DES'CRIPTION OF EVENT 2-84012 During. surveillance testing for external piping leakage, both trains of the residual heat removal system were inoperable for-two hours, forty-seven minutes on July 10, 1984 when valve HCV-74-34 (RHR to RWST recire line isolation valve) was opened as part.of the procedure for checking RhR pipe leakage.
Diesel Generator Failure Reports There were no diesel generator failure reports transmitted during the month.
Special Reports
- Special Report 84-03 was transmitted to the NRC on August 7, 1984.
Concerning the inoperability of the fire detector in the mechanical equipment room of the auxiliary building in excess of fourteen days.
4 Offsite Dose Calculation Manual Changes
- Changes in the Sequoyah Nuclear Plant ODCM are described in this section in accordance with Sequoyah Technical Specification 6.14.2.
, These changes were offically approved by RARC on April 24, 1984. See Appendix A at the end of this report for the approved ODCM changes.
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. .. OPERATING'DATATREPORT
. DOCKET' NO.'- 50-327-DATE; SEPTEMBER.5 1984- . .
. . COMPLETED BY M. G..EDDINGS TELEPHONE'615-870-6248 OPERATING: STATUS.
'1.NUNIT'NAME: SEQUOYAH NUCLEAR PLANT, UNIT
- l' NOTES
- 12.'REPORTJPERIOD: AUGUSTD1984 E 3.fLICENSED THERMAL POWER (MWT): ' 3411.0 5
- 4. NAMEPLATE RATING (GROSS MWE) 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.O' l- f64 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0 7.1 MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 8. IF
- CHANGES OCCUR.IN CAPACITY RATINGS (ITEMS NUMBERS
~ 3 THROUGH.7)SINCE-LAST REPORT, GIVE REASONS 3 --__ - - - -
, -9. POWER LEVEL TO WHICH RESTRICTED.IF ANY(NET MWE)t- -
- 10. REASONS FOR RESTRICTIONS,IF ANY
- . - - - - - = - -
l THIS MONTH YR.-TO-DATE-- ' CUMULATIVE i
- 11. HOURS IN. REPORTING PERIOD 744.00 - 5855.00 27792.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 718.50 . 3394.60' 17836.16'
- i. '13. REACTOR RESERVE SHUTDOWN HOURS 0.00- . O . 00 - OJOO
! ~14. HOURS GENERATOR ON-LINE: 701.25- 3223.05 17336.20'
, 15. UNIT RESERVE SHUTDOWN HOURS 0.00 10.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 2301819.21 9936808.18 - 55428658.48
-[ :17. GROSS ELECTRICAL ENERGY' GEN. (MWH) 746040.00 3245990.00 18625126.00 '
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- 18. NET ELECTRICAL. ENERGY GENERATED (MWH) 716572.00 3108379.00 . 17885307.00
- 19. UNIT SERVICE FACTOR 94.25 -55.05 62.38
'20. UNIT AVAILABILITY FACTOR 94.25 55.05 62.38 21.- UNIT CAPACITY FACTOR (USING MDC NET) 83.90 46.25 56.06
- 22. UNIT' CAPACITY FACTOR (USING DER NET) 83.90 46.25- 56.06
- 23. UNIT FORCED OUTAGE RATE 5.75 28.27 20.09 L24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND. DURATION OFJEACH):
- ---- ____ _- _-- ___=- ---- --= ,
f 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 1 __ - _ -
4 NOTE THAT THE THE YR.-TO-DATE AND '
CUMULATIVE VALUES HAVE BEEN UPDATED. !
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UNIT SHUTDOWNS AND POWER REDUCTION 3- DOCKET NO. 327' UNIT NAME- seauovah one - -
DATE september 5. 1984 -
COMPLETED BY M. G. Eddings -
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REPORT MONTH AUGUST TELEPHONE (615) 870-6248
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- 57 "$: c yt Licensee y Cause & Corrective No. Date E O$ 8 iO2 Event @ *c., E*o Action to R Ej 2 5y" Report ? M3 &T Prevent Recurrence 5" ?N5 N* 8" u
E 13 840827 F 42.75 A 3 . Reactor trip-steam flow /feedwater flow mismatch loop #1 feedwater regulator valve failed close.
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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
, .; 3 AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO. 50-327~
UNIT lSequoyah One DATE Septembsr 5. 1984
, COMPLETED BY M. G. Eddings TELEPHONE (615)870-6248 s,
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MONTH AUGUST DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,
1 1081 17 - 1063
, 2 ings 18 1062 3 1080 t 19 1063 4 1079 20 1060 _
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5 '1078 21 106'2
6 1074 22 1061 7 1074 23 1061 8 1076 24 1060 9 1075 25 1063 10 1074. 26 1064 11 1075 27 1040.
- 12 1073 28 N/A 13 1072 29 173 14 1069 30 280 '
15 1066~ 31 95 ,
16 1065.
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INSTRUCTIONS
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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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i 2 OPERATING DATA REPORT ,
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DOCKET NO. 50-328_ '
i DATE SEPTEMBER 5,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6248 OPERATING STATUS
- 1. UNIT.NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORT PERIOD: AUGUST 1-31,1984
- 3. LICENSED THERMAL POWER (MWT): 3411.0
.4. NAMEPLATE. RATING (GROSS MWE): 1220.6 5.. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:-
- 9. POWER LdVEL TO WHICH RESTRICTED.IF ANY(NET MWE):
- 10. RhASONS FOR REETRICTkONS,IF ANY: .=
-=
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.00 5855.00 19752.00 ,
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 514.30 5549.70 15910.77
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE 496.55 5455.62 15609.94
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL-ENERGY GENERATED (MWH) 1626829.80 17978339.65 50396407.46
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 538060.00 6138350.00 17170290.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 516879.00 5914343.00 16532080.60
- 19. UNIT SERVICE FACTOR 66.74 93.18 79.03
- 20. UNIT AVAILABILITY FACTOR 66.74 93.18 79.03
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 60.52 87.99 72.91
- 22. UNIT CAPACITY FACTOR (USING DER NET) 60.52 87.99 7 2~. 9 1
-23. UNIT FORCED OUTAGE RATE 33.26 5.90 8.11
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Re.fuaUng/ModificALisn_0 tage____ 3t Cycle 2 _Setpember 2 21, 19_84, 56_ day _s . _ ,__
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two- -
DATE- September 5. 1984 .
COMPLETED BY D. C. Dupree -
REPORT MONTH AUGUST TELEPHONE (615)870-6248
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- 57 "e c Et Licensee $ Cause & Corrective N. Date [ t$ 8 iO5 Event 6% E4 Action to
@ 2E 2 5y* Report # Mi &T Prevent Recurrence 5~ ?@5 N" "
2 6 840820 F 234.80 A 1 ,
Ruptured the diaphram in the pressurizer relief tank. PRZ relief valve leaking.
7 840830 F 12.65 G 3 Unit operators over fed the steam generators
,L causing the' turbine and reactor to trip.
T 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
. s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. s0-328 UNIT .q;,,,,nymw s,n DATE sonenmsnr s 1984 COMPLETED BY D. C. Dupree TELEPHONE' (615)870-6248 MONTH- AUGUST DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1098 17 -
1093 2 1098 18 1062 3 1096 19 1090
-4 -
1095 20 '1078 5 -
1094 21 N/A :-
6 1093 22 N/A 7 1095 23 N/A 8 1092 24 N/A 9 1094 25 N/A 10 -1095 26 N/A 11 1096 27 N/A 12 1096 28 N/A 13 1097 29 N/A 14 1098 30 5 15 1095 31 239 .
16 1094 INSTRUCTIONS ,
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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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.- Plant Maintenance Summary The following significant maintenance items were completed during the month of August 1984:
Mechanical Maintenance
- 1. Installed a furmanite box on the orifice flange of 1-FE-3-163 and injected with Furmanite to'stop a leak.
- r. 3. -Completed work on the.2D cooling tower lift pump and repaired welds on the 2A mixed bed demin tank and associated piping.
- 4. The condensate demineralizer waste evaporator heater was found to have a broken weld and a crack in the shell. Vendor representatives from HPD, Inc.
assisted in the repairs.
- 5. Perform SI-102 monthly inspections on the.1A-A, IB-B, and 2A-A diesel generators.
- 6. Replaced the IA-A high pressure fire protection pump with.a spare pump
~due to worsening base-line data recorded during SI-73. The defective pump is being rebuilt for use as a spare pump.
- 7. Pressurizer safety valve 2-VLV-68-563 was replaced with'a spare valve due to excessive leakage. The defective valve is being rebuilt and tested for use as a spare valve.
- 8. Welded a scab plate to the ERCW piping above the "B" component cooling system heat exchanger due to a leak caused by cavitation erosion in the system.
- 9. Replaced 2 rupture disks on the pressurizer relief tank found ruptured during inspection and maintenance.
-10. Began rekeying plant doors due to the loss of some important keys. These doors include CSSC and non-CSSC doors in all areas'of the plant.
- 11. Replaced'a broken nipple on the CCS heat exchanger vent valve.
- 12. Removed the RHR hot leg injection relief valve 2-LVL-63-637 thought to be leaking and verified'it to be within the setpoint range.
- 13. Replaced a leaking drain valve 2-VLV-68-568 for the pressurizer safety valve-2-VLV-68-565 loop by welding.
- 14. The SIS pump suction check valve 2-VLV-63-510 failed an SI. The valve was disassembled, inspected, reassembled and retested successfully.
- 15. Replaced the solenoid on 2-FSV-62-9.
g _16. Replaced the relief valve on the 1D1 feedwater heater.
- 17. -Rebuilt the solenoid on 2-FSV-90-109. i
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Plant Maintenance Summary Electrical Maintenance ~ Page 11 of 4 ~
10:59:16 09-11-84 ELECTRICAL IENTit.Y REPORT PAGE 1 :1 DATE..._ CGPONENT. . . . . FAILLRE DESCRIPTION...... CAUSE OF FAILURE.........- CORRECTIVE ACTION........ PRON.... . .
<94-09-0 1-90C-201-JN/1 BREANER SLPPLY FDR 480 ! MORT IN CABLE LEAVIM; REPLACED BREANER'PER NOE ',
3 1E2 VOLT RECEPTACLER IN PAEL (CABLE WAS flAINTANCE INSTRUCTION CONTAlleENT AM) AUXILIARY REPAIRED ON ANOTER 6.20 BUILDING TRIPPED AM) rgt)(CABLE REPAIRED WAS >'
SMONED M3T CSSC) 84-09-2 0-9CTD-065-004 OVERLOAD EATER ON EGTS IRONG OVERLOAD lEATER WAS REPLACED OVERLOAD EATER. . HOE
, 3 2-9 TRAIN 8 FAN B-B 110 TOR INETALLED 42227 WITH DVERLOAD MICMS 110 TOR DUT CAUSING EATER 42324
- FAN IGT TO OPERATE
! 84-06-0 . 2-HS-067-0126- LIGHT BLA.B 11ISSING BLt.B BRONE LEAVING BASE REMOVE 0 BRONEN BULB AM) . NOE .
. 8 B (F BULB IN SOCNET REPLACED WITH EW BLA.B .
4 84-08-0 0HA.V-311-0021 A.H.U. "AA" M.RIIDITY ELECTRICAL CONTACTS ON . CLEAE0 Ale LUBRICATED NDE
-8 CONTROL VALVE WILL NOT lETOR WOULD NOT 11ANE MOTOR .CLEAED ELECTRICAL I OPERATE WEN A SIGNAL IS CONTACT CONTACTS AM) REINSTALLED GIVEN FEITOR 84-06-0 1-9NRC-201-NE/ BREANER B203 ON 410 VOLT TRIP COIL BLRHT UP DEAD TRIP COIL WAS REPLACED ON IDE
- 9. 203-A SitJT DOWN BOMtD SHOED A Gt0lH) AMOTER 11t l
GROIM)
- 11 4
B-9 fECHANICAL OVERSPEED TRIP 11AINTANCE VERFIED THAT RELAYS (OST) ON DIE!EL 2B-8 SDR,SDRX AM) SDRX1 PICNED ,
PREVENTS STARTING LP AM) THAT DIESEL WOLR D SIfRLATE A TRIP SIGNAL NOT START RESET TE SitJT DOWN RELAYS 84-08-2 2-FSV-067-0350 FLOW SWITCH ON FAN 2B FLOW SWITCH DIRTY RENOVED Ale CLEANED FLOW NDE 3 WDd.D CYCLE IN STAl@BY CONTACTS SWITCH CONTACTS ~
POSITION 84-09-2 2-HS-067-0124- GREEN LIGHT WILL M)T STAY PIN BRONEN ON SOCNET FR0ff - PIN WAS REPLACED ON. IOlE 3 B ON CONTAlltENT IFRAY GtEEN LAMP OF CONTAIltENT ANOTER f5t .
CONTROL SLPPLY VALUE 1 PRAY SUPPLY VALVE 8 N18-2 0-05t-311-0171 FREON LOW LDW ON FREON IN SIGHT ADDED FREON TO PROPER NOE i
- 3 GLASS NO FAILLRE LEVEL 84-08-2 2-HS-063-0147 RED LIGNT ON NAle SWITCH LIflIT SWITCH (M VALVE IN ADJUSTED LIMIT SWITCH NOE I
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Plant Maintenance Summary
.Page.2 of 4[
Electrical Maintenance ,.
10:59:16' 09-11-84 ELECTRICAL PO m LY REPORT ~PAGE 2.
. DATE...- CG90NENT. . . . . FAILL5tE DESCRIPTION...... CAUSE OF FAILIAtE. . . . . . . . . CORRECTIVE ACTION........s PRON.... .
3 UILL NOT ladtK- ' M ACClfMLATOR RGOM OUT ACTUATION ROD -
(F ADJUSTFENT
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[ 84-09-2 04fTCK-234-030 ALARM ON EAT TRACE TD PERTlNtE CONTROLLER REPLACED TD9ERTURE ' NDE ,,
i~3 CP TD9ERATtNtE CONTROLLER ON SOCNET ON CNT ALARM (F CONTROLLER SOCKET CYCS IS ON CVCS IS BAD l
! 84-07-2 OfCV-077-0145 "G" WASTE GAS DECAY TADOC BAD SOLENOID COIL ON REPLACED SOLENDID COIL NDE
- .3 -A 'VALUE WILL NOT OPEN VALVE 84-9-31 1-C0f9-061-001 GLYCOL CHILLER PACKAGE B le TROUBLE Foule (BSERVED C0f9RESSOR FOR N0tE 2-A CorPRCSSOR TRIPS OUT E HOLR NO TROLBLE FOIAC 4
84-07-3 0-XS-013-0160- IPOICATOR BtLB IN EAT BlLB BAD . REPLACED DOICATOR BUL8 .NOE 1 D DETECTOR IN FAN ROOM EL 714 DOES NOT BtstN 84-07-3 2-HTCK-234-002 LIGHT STAYS ON C.V.C EAT le FAILURE GiSERVED ALARft LIGHT FDIt IDE j 1 8-P . TRACE SHOWING ALAitti GE HOUR WORKED PERFECTLY
- 07-3 2-FSV-001-0025 STEAft GEERATOR BLOWDOWN le FAILURE IBSERVED BLOWDOWN VALUE POE 1 -8 VALUE SHOWED 100 VOLT FDR GROUlO APPROX. ONE
< GROUlO LOUR WORKED OK i
- 84-07-3 1-flTRB-313-00J 18 480 Vol"7 CrM R00ft LOW OIL LEVEL ADDED 1/2 CAL. OF 4GS OIL NOK r j ,1 G AIR HAIOLING r d CHILLER j PACKAGE STAR"f' r.n RUNS 1 FOR APPROX. *. %~~PW3 i
TEN TRIPS 07. av e.c8 GIL
- - PRESSURE
,.84-07-3 0-LOCL-013-061 ALAltM LIGHT DOES NOT BlRN FAULTY ALAltM LIGHT REPLACED ALAltM LIGHT IGE '
j .1 6 ON CP 30 84-07-3 0-XS-013-0151- SMOKE DETECTGt DOES NOT BAD DETECTOR - REPLACED DETECTOR ON lOE j 1 D W0ltK IN EU FLEL STORAGE XS-13-1510
- mm t
i 84-07-3 2-LOCL-013-062 ALAltM HORN ON CP30 ICT BAD HORN HDRN IMS REPLACED ON NOE -
l 1- 2 WORKING ANOTER 11t ON PANEL IOltN, WORKING OK HOW i
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v Plant Maintenance Summary . ..
Electrical Maintenance. , . .Page 3 of 4 ^ * -
.10:59:16 09-11-84 ELECTRICAL MONTM.Y REPORT PAGF 3- .
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.DATE... - C9PONENT.....- FAILlRE DESCRIPTION...... CAUSE OF FAILLRE. . . . . . . . . CORRECTIVE. ACTION........- PRON. . . . . _.
84-07-3 . 0-LOCL-013-061 ALDIBLE ALARl1 DOES NOT BAD ALARM ALARM WAS REPLACED ON NOE ,
, 1 9 WORK ON PYRONTICIS PAEL ANOTER IWti WORKING :
- 619 (XIRRECTLY NOW 84-07-3 0-XS-013-0150- WITE LIGHT DN DETECTOR BAD IlOICATOR LIGHT BUL8 REPLACED IMICATOR BULB NDE -
1 A IN CASK LOADDC AREA DOES NOT COE ON 84-07-3 0-05t-031-0338 BOARD ROOM CHILLER SAFETY SWITCES l'.AY HAVE le TROUBLE FOUM M WORK . NOE L 1 l-A PACKAGE B-B WILL NOT SEEN STICKING PERFORf1ED e
START-I j 84-07-3 1-f1TRB-031-E/ 480 UOLT BOARD ROOM le FAILURE CECNED FREON, FREON WAS NOK 1- 11D-A CHILLER LOW ON FREON NORl1AL 84-07-3 2-ZS-062-0118- BOTH LIGHTS STAY ON ACTUATOR ARM ON LIMIT ADJUSTED LIf1IT SWITCH ARl1' ICIE 2 1 A REGARDLESS OF.VALV SIITCH OUT OF ADJUSTENT
, POSITION OF LET DOIM .. . ;
i VALUE 0118-A i
84-07-3 2-ZS-062-0192- LIMIT SWITCH ON B LIMIT SWITCH OUT OF ADdUSTED LIMIT SWITCH MOE i 1, B EVAPORATOR RECIRCLA.ATING ADJUSTENT
- VALVE WILL NOT WORK 84-07-3 ' 2-ZS-062-0164 -8 EVAPORATE BORIC ACID #1 LIMIT SWITCH DUT OF ADJUSTED LIMIT SWITCH NOK i 1- COEENSTRATE PLNP SUCTION ADJJSTENT
! VALVE WILL NOT WORK o l 84-07-3 1-ZS-062-0192- 'A BORIC ACID EVAPORATE LIMIT SWITCH ON VALVE OUT ADJUSTED arf 1 DN LIMIT NOE l1 D , RECIRCtLATING VALVE WILL NOT WORK (F ADJJSTENT SWITCH j '1
! 84-07-3 1-LS-077-0411 POCKET Surp LEVEL CABLES AltE SUSPECTED TO CECNED Our CIRCUIT A>D NDE l1 INSTRUENT LOOP WILL NOT LET Purp 1A RUN BE ROLLED FUNCTIONALLY TESlED FOR PROPER OPERATIONS FOUND
- le PROBLEl1S
) 84-07-3 2-XS-013-0155- STENE DETECTOR ON ER10KE DECTOR DEFECTIVE REPLACED SrWNE DETECTOR NOE l 1' B XS-13-1558 WILL MIT j (PERATE ON PAEL 611 i
0-CMt-031-0338 BOARD ROOM WATER CHILLER BAD OIL HEATER BREAKER REPLACED DIL EATER- NOE f84-07-3 1
P Plant Maintenance Summary Electrical Maintenance Page 4 of?4 '
10:59:16 C9-11-84 ELECTRICAL PENT)t.Y REPORT - PAGE 4 FAILIRE DESCRIPTION......
DATE... CG90NENT. . . . . CAUSE OF FAILURE......... CORRECTIVE ACTION........ . PRON....- .
1 -A B-8 OIL tEATER RELAY WILL ' BREAKER .
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NOT STAY IN LAEN UNIT IS OFF
- E31 records . listed.
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Plant Msinten.nce Summary l
. (Continued)
Instrument Maintenance-
=
g ~ 1. .During the month,~there were.no-spurir.us actuations of. containment vent' or auxiliary building vent.isolations for either unit. There was a unit 1.-
containment isolation.and'a train A. isolation of the axuiliary building .
t on August' 30; 1984, as a ' result of loss 'of' AC. power to train A rad monitors
- -during maintenance -on~ the' lower containment Iodine rad monitoring channel.-
The addition of the time delay relays to the actuation circuits have proved to be effective.
, 2. The' monthly calibration check'of the UHI level. switches found unit 1 i switches, LS-87-21 da LS-87-24 out of' tech spec tolerance. All unit 2' switches were within tech spec tolerance.
Unit 1 i .
- 1. On August:15, 1984,- pressurizer level channel L-68-320 began reading i 'high. The constant head condensate pot was vented to bring the channel
- within tolerance of' the other channels. On~ August 27,' 1984, channel i L-68-335 was reading low. Sense lines and drain lines were checked for l leaks but none.were found. The condensate pot for channel.L-68-339 was i
backfilled to bring.all. channels within tolerance. Following the unit trip, LT-68-320 was calibrated and backfilled. After the unit startup',
channel L-68-320 was'. vented again on August 30, 1984.
- 2. 'On August-15, number 2 governor valve control channel experienced spiking.
. Changing out -both speed error cards did not correct the problem. Following
} the unit trip, th'e B speed' channel card was replaced and calibrated. On-i August 30, 1984,.when the trubine was being rolled for startup, the new
, B speed channel card, failed. The original card was reinstalled and.the ,
i unit brought on line. Troubleshooting all repairs are planned during the next forced outage.
t Unit 2 i
, 1. On August 8, 1984 during performanced of the monthly test of reactor
[ protection system logic, the reactor trip breaker tripped out of' sequence.
- Troubleshooting discovered a shorted input diode in the testing circuit which caused actuation of the breaker during testing. The bypass breaker was in service during the test so the ' unit was not affected.
! 2. While the unit was in the forced outage to replace the leaking safety l valve; both level channels'for the PRT were verified. LT-68-300, the normal channel was within tolerance at lower range but was high at'the 100% point. LT-68-312C,'the backup channel, required calibration due
! to normal 'drif t. The accoustic monitoring and safety valve tailpipe l' temperature channels were functional tested and found to be operable.
-3. On August'22, 1984, after the unit reached mode 5, NIS source. range channel N-32 developed noise. The detector assembly for N-32 and intermediate range channel N-36 was replaced. New plateau curves were plotted and the I
channels were recalibrated and returned to service.
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Plent Mainten nca Summary (Continued)
Instrument Maintenance (Continued)
Unit 2 (Continued)
- 5. Throttle: valve number 2 remained close until August 14, 1984. It was decided to determine if the valve would stay closed if EHC oil was reestablished. The valve came open and remained stable until August 20, 1984. The EHC oil was isolated and the valve remains closed.
Repairs are planned during the upcoming refueling outage.
- 6. Other maintenance work is shown on the attached list.
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Plant Maintenance Summary ,
Instrument Maintenance Page 1 of 3 INSTRLf1ENT f1A!NTENANCE t10 NTH.Y SUrt1ARY 09-11-84 PACE 1 l C0rP .
FIR.C0rp U FUNC SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCRR ECTIVE ACTI0N. . . . . . . . . . . . . . . . . . . . . . .
lA093133 0 FE 030 149 08/10/84 0-FC-030-149, CALIBRATE LOOP AND VERIFY TE AUXILARY BUILDING GAS TLRBIE SWITCH SETPOINT. m@RDN EXHAUST FAH A-A VACClft RELIEF FLOW CONTROLLER WASLow RM A LOOP CECK M ,,
CALIBRATED THE CURRENT TO PRESSURE PER VENDORS flANUAL.
!A093124 0 FE 030 148 08/10/84 0-FC-030-149, CALIBRATE LOOP AND VERIFY CAL. VERIFIED PER ENGt. VERIFIED CAL.
l SETPOINT. n>FRDu HO PR08LEttS FOLAG.
!A121391 2 LI 068 300 08/23/84 2-LI-068-300, CHECK PRT LEVEL TRAuIuCECK PRT THE REACTOR COOLANT PRESSlRIZER RELIEF l LEVEL TRANSt1ITTER CALIBRATION PRIOR TO TANK TRANSrf! ITER WAS REGLESTED TO NAVE REPLACErENT OF DIAptstAGN AIO AFTER TE DIAPNGRAN A CALIBRATION VERIFIO4 TION. TE l
IS REPLACED. TRANSf1ITTER WAS F0lRe OUT OF i CALIBRATION DUE TO NATURAL CALIBRATION DRIFTS. RECALIBRATED T E TRANSFIITTER VERIFIED OPERATION AFD RETtRED TO i SERVICE.
IA121555 1 LIC 003 148 08/28/841-LIC-003-148,LIC ALLOWS 125 OPEN FLOW l#EN S/G THE STEArt GENERATOR 10 CONTROLLER WAS 3 LEVEL IS AT 58% ADO TE CONTROLLER IS IN AUTO. ALLOWIts CE RAGRED Ale TENTY FIVE ,
GALLONS PER FIIDRJTE F1DW. REPLACED THE l CAPACITOR ON TE VOLTAGE TO CURRENT BOARD VERIFIED OPERATION ADO RETURED -
TO SERVICE.
- A230682 1 FT 002 256 08/06/841-FT-002-256,REr10VE 1-FT-2-256 FR0ff SERVICE PER A REGlEST WAS F1ADE TO CHANGE TE TACF 1-84-85-2. INSTALL NEW FCI fl0 DEL LT81 TRANSi1ITTER TO A EWER FIODEL. TE TRANSf1ITTER PER TACF. TRANSilITTER WAS CHANED, CALI8 RATES AND RETURED TO SERVICE.
A238885 2 FCV 032 103 08/07/84 2-FCV-032-103.2-FCV-32-103 WILL NOT STAY OPEN WOLA.0 DET STAY OPEN DJE TO TE PRESSLRE I WEN 2-FSV-1038 IS DEENERGIZED INDICATOR CONTROLLER NOT WITHIN I CALI8 RATION LIrlITS. RECALI8 RATED TE PRESSURE I6CICATOR CtNTROLLER, VERIFIED l
1 OPERATIDH ADO RETL5 TIED TO SERVICE.
A239830 1 ift 068 3700 08/15/84 1-Lil-068-3700,0UTPLIT OF 1-Lrl-68-3700 NAS FAILED THE REACTOR LEVEL WIE RME LEVEL
] LOW. EEDS TO BE ItEPAIRED. INDICATOR WAS REPORTED FAILING LOW.
THE CIRCUIT CARD WAS F0ule WITH A BAD OPERATIDHAL At1PLIFIER. TE J OPERATIDHAL AFPLIFIER WAS INSTALLED
{ OPERATION WAS VERIFIED Ale RETURED TO l SERVICE.
S A239ye 2 TI 074 49C 08/24/84 2-TI-074-40C.ISOICATOR WAS STICKING LAEH SI 87 THE INDICATOR WAS STICKING DLRING TE I WAS PERFORr:ED. LEEDS TO BE REPLACED. PERFORl1ANCE OF A SUREILLANCE
! INSTRUCTIONS. REPLAED TE CAUGE WITH A i EW INDICAMR CALIBRATED Ate RETLRED TO j N*d.
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Plant Maintenance Summary Instrument Maintenance Page 3 of 3 .
INSTRLFENT F1AINTENANCE f10NTM.Y SlM1ARY 09-11-84 PAGE 3 COW *
. c ret. COW U FUNC SYS A00RESS. DATE. . . . DESCR IPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCRRECTIVE AC TION. . . . . . . . . . . . . . . . . . . . . . . ~
I A9Y. OPERATION ADO RETURED TO SERVICE.
A285942 1 Rf1 090 1000 08/27/841-Rf1-090-1008, RAD r10NITOR 1008 FOR SHIELD BLDG CHECK SOURCE STICK!)E DE TO BENT WIRE.
WONT SOURCE CECK CORRECTLY STRAIGHTEED WIRE 1 FREED CECK SOURCE. ,,
A291030 1 H2AN 043 200 08/09/841-H2AN-043-200,1% N2 CAL GAS BEIDE DEPLETED LEAKING FITTING. TIGHTEED FITTING.
RAPIDLY 1
A291032 0 Q.AH 043 205A/205 08/11/84 0-CUH-043-205A/205, REPLACE CLASS ORIFICE IN STOPPE0 UP FLOW ORFIES. REPLACED i j EACH DETECTOR (TRAIN "A" & "B") ORFICES 8 TESTED.
, A291045 2 043 210 08/28/84 2-043-210,INDICATDR READING .3% HIGER THAN INDICATOR OUT OF CAL. RECAL IlOICATOR.
1 ANfd.YZER.
A293174 1 LI 068 335A 08/28/84 1-LI-068-335A, min LEVEL INDICATOR IS DRIFTING AIR IN LIES. BURPED SENSE POT TO 00lm REl10VE AIR.
I A293177 1 PCV 047 190 08/29/84 1-PCV-047-190, uIu (M.DADE]t VALVE IS Uta.0ADER DUT OF ADJUSTfENT. ADJUSTED F1ALFIMCTIONING MIT f1AINTAINING SYSTEl1 PRESSLNtE (M.0ACER "A" & "8" 8 RELIEF.
l PRWERLY.
A293236 2E 092 5002 08/24/84 2-XE-092-5002, INVESTIGATE AM) REPAIR AS EEDED - THE SOURCE RAIGE DETECTOR CHAT #EL N32 TE DETECTOR HAS M LMCONTROLLED INCREASE IN CPS WAS REPORTED INCREASDE IN COUNTS PER
! SECOM) AT A RAPID RA1E. REPLACED TE i DETECTOR RECAL18 RATED AM) RETLNtED TO SERVICE.
i 26 records listed.
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' Plant Maintenance Summary (Continued)
-I Modifications Group
-1. ECN 5237- Laundry Facility The work on the HVAC continued. The duct work was completed except testing and completion. of the air plenum around the. dry cleaners. The mechanical' tie-in for the chiller package was completed. The fans are being tested.
- 2. ECN 5645 - Steam Generdtor Blowdown System - Unit-2 During the recent unit 2 outage final tie-ins were made to the blowdown-line for the heat exchangers, the drain to the turbine building sump and some instrumentations connections. Work continues on the remaining instrumentation and insulation installation. All non-outage electrical work is complete.
- 3. ECN 2768 - Reactor Pressure Vessel Level Indication System (RVLIS) (Unit 2)
During the unit 2 outage a major effort was made to finalize routing 4
details inside the crane wall. Some hangers were installed in the raceway.and inside the crane wall. Work has been completed in the annulus g and penetration. room. Since the outage prefabrication. work has begun utilizing the details obtained during the outage, all workplans have been written and approved except one which involves a vendor procedure not yet recieved. All outside containment conduit is complete.
- 4. ECN 6055 - Wide Range Pressure Transmitter to the RVLIS Panel Mechanical work is in progress. Conduit work continues. Cable pulling and termination workplans are being prepared. ENDES and instrument maintenance are making changes to the unit 2 control room indicators.
The control air tie-in was-made during the unit 2 outage. Installation of
- lead brick which is on order is the only mechanical activity remaining.
All electrical work in piping room is complete. Work is in progress in MCR.
j 6. ECN 5024 - Lay-up Water Treatment i
During the unit 2 outage, one of two hangers was installed in the west valve room. A detailed walkdown of the area in the valve room was also performed. The pipe prefabrication continued and is approximately 50% complete. Electrical work remaining includes heat trace installation and function testing of the pressure switches.
- 7. ECN 5009 - ERCW Piping Change-Out Prefabrication of piping for the installation of stainless steel pipe for the centrifugal charging pump room coolers continues. Installation is planned ~for the unit 2 cycle 2 refueling outage.
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Plrat haintenance Summary (Continued)
Modifications Group (Continued)
- 8. ECN 5202 - Interfacing the Diesel Generator Buildings and the Power House Workplan preparation c >ntinues for the ERCW tie-ins required for the diesel generators.
- 9. ECN 5842 - Replacement of PCV-3-122 and -132 Field work was started on three hangers. Additional work to be performed during the refueling outage.
- 12. NUREG 0588 ECN L5457 Remaining items are scheduled for the outage.
ECN L5895 Solenoid changeout will begin as soon as new splicing procedure is approved.
ECN L6032 H2 analizer relocation - during the outage the shield building penetrations were installed. Tubing work continues in both the auxiliary building and annulus.
ECN L5883 Pres. switch reloaction - piping work in the auxiliary building was started. It is planned to be cc.npleted before the outage scheduled September 21, 1984.
ECN L5881 Work began on fabricating brackets for limit switches.
ECN L5823 Six pressure switches have been changed out.
ECN L5824 Seven of 125 valve operators have been replaced.
ECN L5370 Workplan 10617 - 15 of 16 motors replaced. Sixteenth motor is awaiting repair or to be transferred in from IIartsville.
ECN L6200 Press. transmitter relocation - this workplan was written, approved and work started. Tubing work continues and is anticipated to be completed by September 21, 1984.
A flow transmitter for L5884 has been reordered.
- 12. ECN 6182 Workplan preparation was started and contractor scheduled to arrive during August.
- 13. ECN 5664 - Wells Fargo AS-24 Cards Relay Change-Out Field work on the boxes and CAS/SAS terminations work continues.
Cable pulling is in progress.
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Plant Maintenance Summary (Continued)
. Modifications Group (Continued)
- 14. ECN 5172 & 5968 - Emergency' Lighting-SDFWP, AFP, FW REG VLVS and MS Power Operated Relief VLV Areas Installation of new conduit, strobe lights, and sirens continued.
Estimated completion of WP 10578 is around mid October if worked during upcoming' unit 2 coutage.
- 15. ECN 5770 - Installation of New Rad Monitor in the Condenser Exhaust Work in pane 2-M 3D is in progress.
- 16. ECN 5867 - Unit 2 Spend Fuel Transfer System Westinghouse modifications are complete nn the pit side and work is complete on reactor side. Functional test is underway.
- 18. ECN L2780- Post Accident Sampling Facility Unit 2 The HVAC duct work is installed and hanger work continues. Test running of the. system is scheduled for this month. Miscellaneous tubing work continues. Sealing of the enclosures was started and continues. The Fire Protection System tie-in and hydro testing was completed. During the outage, a walkdown on-the containment work was performed. Electrical systems are 95% complete. Functional testing of HVAC has commenced.
- 19. ECN L5198 - Technical Support Center (TSC) Unit 2 The control building conduit installation on elevation 685 is complete.
DPM 50 and P250 tie work is continuing as well as cable installation.
- 20. ECN L5723 - Condensor Sparger Relocation
- Outage prefabrication was started and compledted uring this time period.
The remaining work will be completed during the U2-C2 refuel outage.
- 21. ECN L6050 - Hangers For Fire Protection L The work is 99% complete.
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- 22. ECN L6071 - Installation of Shield Wall El. 690 This wall was formed and poured during this period. Paint work remains.
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Plant Maintenance Summary (Continued).
Modifications Group
'(Continued)
- 23. .ECN L5552 - Hi Crud Filter System Modification The system was declared manually operable on September 1, 1984 and met TVA's commitment to EPA. Pre-op testing of the systems continued for the automatic operation of the system. Overall 95% of the work is complete.
U24. ECN L5841 - Hot Machine Shop Modifications All civil.and mechanical decipline related work is complete. Electrical-power supply ' for the machine shop and decon shipment is continuing. EN DES engineers are evaluating field conditic- o provide a monorail and hoist over the electro polisher equipment. Overall 95% of the work is complete.
- 25. EN DES Office Complex EN DES office complex buildings are complete and the majority of the EN DES engineers have occupied the buildings. Outside work line grading drainage, sidewalk, fence, etc. continuing.
- 26. Common Service Station Transformer "D" Transformer "D" is ready to be energized as soon as the fire protection spray valve is' repaired.
- 27. ECN L5503 - Office and Power Stores Building Work is overall 85% complete.
- 28. ECN L5599 - Fifth Vital Battery J
, Workplan preparation to perform tie-in to existing boards is continuing, i-
- 29. ECN L5609 - Water Treatment Demin Water Storage Building Overall 90% of the work is complete.
- 30. ECNs - L5933, L5934, L5935 - Security Power Block Overall 75% complete.
- Contractor - Cooling Towers Repair Custodis Ecodyne Inc. continued working on the cooling towers repair work. At ;
this time cooling tower B is being repaired. All fill (plastic and metal)
, material that was damaged during last winter has been removed, permission from the Departmant of Public Health, State of Tennessee, has been obtained for disposal of the damaged material at Hamilton County Landfill.
i APPENDIX A SEQUOYAll NUCLEAR PLANT ODCM CllANCES CilANCE 1 Description of change The comment expla'ining the conversion from mrem to rem was moved in front of equation 2.13 on page 22.in order to clarify the dose equation.
No model changes are reflected in this change; therefore, no evaluations are necessary.r CllANCE 2 Description of change A previously omitted conversion factor of 0.1 was added to the list of definitions following the equation on page 24. No moccl changes are reflected in this change; therefore, no evaluations are necessary.
CIIANCE 3 Description of change The isotope f'ractions appearing in equation 2.18 were changed. The changes appear on page 25.
Analysis or evaluation justifying change The fractions used previously were found to exclude a conversion factor of 0.1 necessary to correct the units and had not been divided by the factor of 0.95 found in the equation.
Evaluation of accuracy of dose calculation or setpoint determination This change will have no effect on calculated quarterly doses or setpoint determinations.
recreation dose.
It will lower the calculated monthly l
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- APPENDIX A
- SEQUOYAH NUCLEAR PLANT- ,
ODCM CHANGES .
. CHANGE 4-Description of_' change-Table-2.3 was replaced with a newer version in which the format is
~
sor.eewha t different. - No model. changes are reflected in this change; therefore,'no. evaluations' care necessary.: '
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.' SEQUOYAH NUCLEAR PLANT 0FFSITE DOSE CALCULATION MANUAL
', EFFECTIVE PAGE LISTING REVISION 10 D LPage Revision
'^~
'. TOC l'through.. TOC 2 Revision 10
-1?through 2 Revision 6 3 Revision 9 4- Original 5 Revision 3 6 Revision 4 7 Revision 8
-8 through 9 Revision 5 10 ' " " Original 11 .
Revision 5 12 throuth 13 Revision 9 14 Revision 7
.15 Revision 9 E
15a Revision.9 16 Revision 9 16a .
Revision ".
Table 1.1 (2 pages) Revision 4 Table 1.2 (2 pages) Origi'nal Table 1.3 (8 pages) Revision 4 Table 1.4 Revision 9 Table 1.4A (removed from document) Revision 9 Table 1.5 Revision 4 L Tables 1.6 and 1.7 Revision 5 Table 1.8 Original l Figures 1.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Revision 2 19 Revision 7 20 Revision 6 21 Revision 9 22 Revision 10 23 Revision 7 24 through 25 Revision 10 26 through 29 Revision 8 Table 2.1 (3 pages) Revision 7 l Table 2.'2 Revision 5 Table 2.3 (3 pages) Revision 10 Table 2.4 a-c Revision 5 30 Revision 8 Table 3.1-1 (4 pages) Revision 4 Table 3.1-2 Revision 8 Table 3.1-3 Revision 4 Table 3.2-1 (3 pages) Revision 4 Figure 3.1-1 through 3.1-2 Revision 4 Figure 3.1-3 Revision 8 Figure 3.1-4 through 3.1-5 Revision 4
. Figure 3.1-6 through 3.1-7 Revision 8
e ,-
$: -x , ';' APPENDIX-A-
. - . r:f 1
~
.. 7f
" fSequoyah Nucl' ear Plant
" Offsite Dose Calculation Manual ~
/
Dates of. Revisions
(.
Original-ODCM ~2/29/80*
Revision l- 4/15/80**
Revision 2 10/7/80**'
Revision-3 11/3/80, 2/10/81 L Revision 4 4/8/81'and 6/4/81**
11/22/82 (10/22/81, t
Revision ~5' 11/28/81-and 4/29/82**
L
~ Revision 6 10/21/82**
l Revision-7 1/20/83**'
l Revision 8 3/23/83**
Revision 9 12/16/83**--
L-Revision 10 3/7/84**
4/24/84**
l i
i
~
i l
l I
l l
I l
i l
I
- Low Power license for Sequoyah unit 1
[ **RARC Meeting date L
~ ,
! )
e- {
i
c .
_S; F ~.
, APPENDIX A-
.m . .
m .
-gr 1 - --.e, ,e -
,ey, ,u
_.4 _. , . , . _ , ,, _
th D. = dose for the.j J
organ from eleven radionuclides, rem
' j. = the organ of interest (bone GI tract and total body).
, 7-
~ [" .95 = conservative correction factor, considering only eleven radionuclides.
DCF th
= crit'ical ingestion dose commitment t { actor for the j organ of adult or child from the i radionuclide rem /pci, see attached as Table 2.1.
th 5 I..=monthlyactivityingestedofghei radionuclide by the IJ critical age group for the j t
organ, pCi.
I...is described by: .
1J I.. = A. V.. (30) ,pci (2.12) lj 1 1]
Fd-(7.34 x 10tu) where:
A = activity released of i th radionuclide during the month, ,
pCi.
3 V.. = maximum individual's water consumption rate corresponding 13 to-the age group selected for the critical DCF.. above 5
(Adult: 2000 mL/d, Child: 1400 mL/d; Regulatory 3Guide 1.109) 30 = days per month F = average river flow at Chickamauga Dam for the month (cubic feet per second) d = fraction of river flow available for dilution (1f5) 7.34x1010 = conversion from cubic feet per second to milliliters per month.
Considering the conversion factor from rem to mrem ( x 103 ), the dose equation then becomes:
11 Dj = 2.15 x 10' (V x DCF)f) x A f, mrem. (2.13) 5 10 F ,
i=1 Revision 10 2;
i i t
y . .
~
-.~
.r c - ' APPENDIX A' re:
'D = dose to-the total body from plant releases, mrem 1:
'0*95 = 4 radionuclidesc nservative c rrection factor for considering only RDCF. * = shoreline recreation dose commitment factor for the i th radionuclide (mrem /yr per pCi/cm ). See. attached table 2
2.3. (Note
For Cs-137, the dose commitment factor for its daughter, Ba-137m,-is assumed.)
th
(*. = concentration of i radionuclide in shoreline sediment
-(pCi/cm2 ), as described by the following equation (based on equation A-5 in Regulatory-Guide 1.109).
&.1 = 100 RHL.
1 C.
1 W [1 - exp (-A.1
- t)} (2.17)
Where:
100 = transfer constant defined in Regulatory Guide 1.109 RHL. = radiological half-life of the i th radioisotope, days, from table 2.1 C. *
=" concentration of i th radionuclide in the Tennessee River, pCi/mL.
Cf = Af /(F d 7.34x1010)
A. = activity released of i th radionuclide 1
l during the month, pCi F = average river flow at Chickamauga Dam for the month, cubic feet per second d = fraction of river flow available for dilution (1/5) 7.34x10t o = conversion from cubic feet per second to milli-liters per month.
W = shoreline width factor (0.3 for a lake shore, per table A-2 of Regulatory Guide 1.109)
A.* = decay constant of the i th radionuclide
= 0.693/RHL 1 t = buildup time in sediment, assumed 15 years, per Regulatory Guide 1.109 67 = assumed monthly exposure time for maximum individual, h
= 500 h (* 10 h/ week) 0.4 (fractional exposure for yr
..- worst quarter) + 3 (months / quarter) 8760 = conversion from year to hours.
0.1 = conversion factor, m2 . ml/cm 2 1 to' _
Revision 10 3
f ,
APPENDIX A f.. . - - ,.
^The dose equation t. hen becomes D=f(0.00692ACo-60 + 0.00012 Aco-58 + 0.00206(2.18) ACs-134 7 10 +
( 0.00342 ACs-137) 2.3.2.4 Monthly Summary Calendar quarter doses are first estimated by summing the doses calcu-lated for each month in that quarter. Calendar year doses are first estimated by summing the doses calculated for each month in that year.
However, if the ann ial doses determined in this manner exceed or approach 8 the specification limits, doses calculated for previous quarters with the methodology of section 2.3.3 will be used instead of those quarterly doses estimated by summing monthly results. An annual check will be made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in Section 2.3.3. If less than-95 percent of the dose has been estimated, either a new list of 3 principal isotopes will be prepared or a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose is predicted.
2.3.2.5 Dose Projections- .
In accordance with specification 3.11.1.3, dose projections will -
be performed. This will be done by averaging the calculated dose 8 for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
2.3.3 Quarterly and Annual Analysis A complete analysi;; utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in section 6.9 of the technical specifications. This analysis will replace values calculated using section 2.3.2 methodology and will also include an approximation of population doses.
2_.3.3.1 Individual Doses The dose to the j th organ of the maximum individual from m nuclides, '
7 Dj , is described by 5
5 m D
j= D ij k , r m (2.19) 4 k=1 i=1 a m 2 5
=
[(IDCF)q xIik) + [(RDCF)ij k *b ik T k 0 ( .20) i=1 k=1 k=3 !
Revision 10 1
APPENDIX A Table 2.3 Recreation Dose Factors
- Sheat 1 % *
..................... 5wInnIms .................. .................... 5 H C a E L I-t E ..*.********...+.
.................. . (MtEM/ TEAR PE4 UCI/ht) ....*......... ....*... (HREM/ FEAR PER UCI/3CU4RE CENTIMETER) ****.*..%
GI ThYECIO 18 LIVER SKIN Bu4E GI THYR 0!O T8 LIVER SKIN ~
- MUCLICE SCNE M-3 0.00E*C0 C.COE+C0 0.CCE+C0 0. 0 CE + 00 0.00E*00 0.00E+00 C.COE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0CE+CG C-14 0.COE*C0 C.00E+00 0.00E+00 C.CCt+00 0.0CE+CC 0.00E+uu C.uGE+00 0.CCE+30 0.00E+00 0.COE+C0 C.0CE+00. 0.0CE+CC _.a .
ha-22 3.14E+C7 2. 9E*07 2.3CL+C7 2.e7E+07 2.27t+07 3.16E+07 2.76E+36 2.19E+0c 2.01C+06 2.33E+C6 1.99E*06 2.76E+06 MA-24 5.66E+07 5.92E+07 6.22E+07 5.3fc+C7 4.ttt+C7 6.14E*J7 3.9eE+06 4.1CE+00 4.2LE+06 3.76E+06 3.33E+CS. 4.29E+04 ..__N P-32 0.CCE+C0 0.00E+00 0.0CE+00 0.CCE+00 0.COE+;; 0.0C!+00 0.uCE*00 0.0CE+JO 0.00E+00 0.CCE+00 C.00E*C0 0.0CE+00 -
_CR-51___ _ 5.43E+05 3.07E+35 3.30E+05 3.7'E+u5 3.C9t+05 4.5cE+05 .5.*5E+C4 3.0!E+04. 3.39E+C4. 3.a1E+C4 _3.10E+04__4.69E+04 Mu-54 s.57E+J6 7.35E+C6 9.6bE+d6 d.26E+0e 1.24E+07 1.04E+06 7.696+05 6.60E+05 8.69E+05 7.42E+05 1.11E+C6
- 1. tee *C7 2.05E+C6 ME-56 2.33E*07 2.14E+07 1.52E+07 2.07E+G7 1.d1E+07 2.54E+0? 1.33E*06 1.69E*06 1.44E+06 1.66E+C6 1 45E+06 ._
FE-55 3. tee +C1 3.47E+01 6.94t*00 1.ett+02 1.47E-01 3.16E+33 2.71E+01 2.9tE+01 5.96E+00 1.44E+02 1.26E-01 2.71E+C3 1.e4E+C7 1.33E+07 1.23E+C7 1.45E*07 1.23 E +C7
- 1.7 ? E *0 7 1.36E+05 1.15E+06 1.C2E+06 1.20E+C6 1.02E+C6 1.46E+C6 FE-59 1.55E+C5 1.17E*05 1.94E+05 Co-57 2.71E+La 9.5:E+C5 1.e9E*04 1.4SE+Co 1.13E+06 1.75E+06 2.32E+05 1.02E+05 1.7EE+05 1.33E+07. 1.03E+07 8.7!!+06_ 1.13E*07 9.e5E+06 1.43E+07 1.1SE+06 9.36E+05 3.00E+05 .1.03Ee36_8.E2E+C5 1.30E+C6._____
.CO-55 .. 2.62E+07 3 67E+07 2.E3E+06 2.46E+C6 2.23E+06 2.54E+06 2.14 E + 0 6 3.00E+C6 CD-60 3.4sE*07 3 02E+07 2.73E+C7 3.11E+07 m1-63 0.C E+C0 0.00E+00 0.0CE+CC C.CCE*00 0.0CE+CC 0.00E+0C C.00E'00 0.0CE+C0 0.00E+00 0.CCE+00 C.CCE+C0 0.0CE+C0 7.e5E*;6 c.50E+Cs c.94E+06 5.34E+C6 7.93E+06 6.13t+05 5.52E+05 5.22E+05 5.60E+05 4.71E+C5 6.41E+C5
%I-65 c.scE+0a *
. Cu-64 2.63E+CS 2.20E*06 .1.E5E?C6 2.23E+0s. 1.92E+0: 2.c7E+06 2.71E*05 2.11E+05_ 1.7dE+05 _2.14E+05 1.54E+C5 2.59E+:5
! ZA-65 7.99E+0s 6.eiE+06 5.5!E+C6 c.9ec+C6 5.9CE+C6 B.47E+06 6.75E+05 5.43E+05 4.71E+C5 5.65E+C5 4.9EE+05 7.4;E+05
_Z4-69.__ .9.55i+01__6.*9E+C1_ e.0iE+01 _7.12E+C1. 6.CCZ+01 4.51E+01 .9.40E+00 .6.3fE+00._6.0CE+00_ 7.01E+00_.5 9CE+00 _E.35E+C0 45-74 1.70E+05 1.30E+05 1.4CE+05 1.4cE+05 1.10E+05 1.6CE+05 1.36E+C6 1.1CE+06 1.1oE+06 1.12E+06 9.40E+05 1.33E+06 5.43E+C5 5.73E+G5 5.6CE+05 4.7CE+05 6.66E+C5 i
, as-7c 3.31E+04 c.o!E+C4 .7.C4E+C4 6.53E+04 5.73E+04 5.12E+04 6.42E+05 ,_
l 54-33 1.12E+05 6.c4E+04 7.24f+C4 e.b1E+04 7.59E+04 1.06E+05 1.07E+C4 5.29E+03 6.95E+03 8.45E+03 7.2CE+C3 1.02E+C4 2.49E+07 1.3CE+06 1.73E+06 _1.79E+06_ 1.65E+06._1.46E+06 ,1.96E+C6 ___ _
sa-54 2.4st+07 2.42E+07 2.59E+07 _2.2aE+07 .2.03E+07 3s-85 2. nae
- 5 2.11E+C5 1.E1E+05 2.39E+C5 2.C4E+05 3.07E+05 2.53E+04 1.EdE*04 1.61E+04 2.13E*04 1.82E+C4 2.74E+04
_ a :-3 3 M ._ 5.24E+02 1.22E+C2._1.22E+02_ 9.46E+02 .3.71E+01 1.13E+C4 4.23E+02 1.1EE+02 5.97!+01. 9.66E+02..1.12E+01__1.23E+C4 8 ER-35M 3.21E+C6 1.3cE+06 1.97t+C6 1.93E*06 1.5CE+C6 2.3CE+06 3.3CE+05 1.39E+05 2.02E+05 1.99E+05 1.54E+C5 2.39E+05 3.22E+03 2.47E+03 2.09E+C3. 2.53E+03 2.1EE+C3 3.03E+C3 If e Et-35 as-86 3.34E+C4 1.29E+C6 2.59E+04 1.04E+06 2.17E+C4 3.73E+05 2.62E+04 1.12E+ 6 2.2eE+C4 9.3CE+05 3.14E+G4 1.42E+ce 1.1CE+05 8.79E+04 7.40E+04 9.50E+04 5.06!+04 1.2CE+C5 25-53 d.99E+C6 9.165+C6 6.1CE+06 3.32E*06 7.33E+C6 9.9CE+06 6.77E*05 6.52E+05. 5.97E+C5 6.24E+05 5.49E+05 7.4fE+C5 _
26-39 2.39E+C7 2.e7E*07 2.41E+07 2.61E+07 2.27C+07 J.17E+07 2.27E+c6 2.0$E+06 1.85E+06 2.04E+C6 1.77E*06 2.49E+C6 54-89 1.33E+03. 1.41E+C3.1.15E+C3_.1.5EE?O3_.1 35E+03 _2.05E+03 1.csE+02 1.24E+02 _1.04E?02,_1 40Et02_.1.19E+02__1 31E+C2 58-90 0.00E+00 0.00E+60 0.CCE+CC 0.00E+00 0.00E+0C 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.CCE+00 0.0CE+0C 0.0CE+00 SE-91 9.71E+C6 7.32E+06 o.32E*06 3.17E+C6 6.9eE+0$ 1.04E+07 E.56E+05 6.43E+05 5.56E+05 7.19E+C5 6 13E+05 _9.13E+C5 Sa-92 1.tei+C7 1.e!E+C7 1.59E+C7 1.7CE+07 1.43E+07 1.93E+07 1.30E+06 1.35E*De 1.28E+06 1.37E+C6 1.15E+C6 1.55E+06 Y-90 1.1CE*C3 2.9CE-C1 1.11E-01 1.32E+GO. 2.77E-02 1.C6E+01 7.97E-01 2.17E-01. 7.6EE-02 9.65E-01 _1.91E-02 7.57E+00
- Y-91 . 99E+04 4.25E+~4 3 77E+04 4.43E+04 3.75E+C4 5.33E+04 4.12E+03 3.51E+C3 3.11E+03 3.66E+03 3.1CE+03 4.41E+03 I Y-G 1 M . _ 7.s3E?06 _e.02E*C6__5.06E?01-_4.21E*06__5.34E+C6 7.53E+06 7.45E+05 5.74E*C5 4.53E+05 _5.93EtC5._5.1CEt05 _7.2CE+C5 . _..
Y-92 3.51E+Co 2. CE+C6 2.49E+C6 3.02!*06 2.576+0e 3.72E+06 3.02E+05 2.39t*05 2.12E+05 2.59E+05 2.2GE+05 3.19E+C5 Y-93 1.30E+Co 1.10E+06 1.1CE+06 9.42E+05 1.33E+06 1.1CE+05 d.91E+04 -8.17E+04 9.13E+C4 7.77E+C4 1.1CE+C5 1.C4E*07 7.7Ei+C6~ 9.91E+05 6.64EiC6'~'d.5cE+06 7.32E+C6 1.0sE+07 9.56E+05 7.13E+C5 6.08E+G5 7.54E+05' 6.71E+C5 9.83E+05 ZA-95 2.27E+C5 22-97 2.57f+Ca 2.04!+0e 1.57E+36 2.1E!*06 1. tee +06 2.62E+36 2.23E+65 1.74E+05 1.6CE+05 1.52E+05 kt-95' 1.03E+C7 ~ d.Cli+0c ~ o.64E*04 't.37E*C6 7.59E+Cf '1.12E+07 9.52E+05 7.31E+05 ~6.24E+05' 6.C9E+05 ~1.6CE*C5 6.92E+C5'~1.02E+C6
_ N S-9 5 M_ _ 1.17E!C6_ 5.59E+C5_ 7.04E;C5._ 7.595+L5 5.90E+C) 9.51E+05 1.22E+G5 5.ocE+04 7.17E+04 5.05E+04 5.90E+C4 1.23E+C5 43-97 v.4CE+C6 7.11E+c6 6.C3E+06 7.o1E+06 o.52t*06 9.43E+0s 6.77E*05 0.63E+05 5.62E+05 7.10E+05 6.CEE+C5 8.79E+C5 d6-97M 1.03E+C7 7.o72+C6 6.54E+0s 5.44E*Je 7.22E+C6 1.CcE+07 9.42E+05 7.03E*05 5.97E+05 7.73E+05 6.c1E+05 9.74E+C5 MO-99 2.41E+Co 1.63E+So 1.52E+C6 1.57E+Co 1.57E+06 2.34E+G6 2.27E+05 1.51E+05 1.43E+C5 1.75E+C5 1.47E+05 2.21E+C5 1
1C-99 0.0]E+C0 C.C*E+c0 ~ a.CCE+CC C.0GE+03 .0.0CE+;C J.00E+00 C.00E+00 .0.0CE+0C_ C.00E+00. 0.00E+00 _C.0CE+0C .C.CCE+CO. . . . .
l TC-95M 2.74E+C6t.03E+06 1.c7E+C6 1.55E+06 1.1:E+06 1.53E+Go 2.83E+05 1.07E+05 1.74E+05 1.6CE+C5 1.21E+05 1.93E+C5 i
. eu-103.. 7.0$i_*C6_ 5.44E+06._4.57E!Ct _).51E+C6.. 4.75E+C6_ e.6CE+06 6.51s+05 5.25E!O5__4.41E+C5._1 32EtC5__4 58E?0L_6.37E+05 au-1G5 1.15E+C7 a.32E+0e 7.34E+06 9.16E+C6 7.79E+06 1.14E+07 1.CDE+06 7.74E+05 6.8&E+C5 s.57E+05 7.29E+05 1.0$E+06 i.40-106 0.COE+C3 0.00E+00 0.0CE+00 0.00t+0J 0.0Ci+0C 0.00E+a0 0.00E*JO 0.0CE+00 0.00E+C0 0.00E+00_ C.00E+00 0.0CE+C0
..l; GH103M 3.73E+C3 4. HEE +02 1.27E+03 2.52E+03 3.92E+02 1.27E+04 1.74E+03 2.1GE+02 5.66E+02 1.36!+C3 1.63E+C2 6.42E+03 2N-105 1.35E+C6 7.56E+05 6.35E+05 9.396+05 7.64E+05 1.12E+06 1.35E+05 7.59E+04 8.41E+C4_9.43E+C4_ 7.67E+04 1.13E+C5 _.
i' antCSM 6.12E+L5 2.1SE+G5 3.75E+05 3.42t+05 2.51E+05 4.51E+55 7.0$E+04 2.30!+04 4.10E+C4 4.11E+C4 2.6eE+04 7.39E+04 l: 2H-106 2.995+C6 _2.30E+C6__1 96E+C6__2.41E+06_ 2.07E+06 _2.93E+C6.___2.31E+05._.2.16E+03._1.34Et05__2.25E?O5__1,24E?Q5__2.74E?05
- . 2G11C4 3.87E*C7 2.97E+07 2.cEE+07 3 23E+07 2.79E+07 4.03E+07 3.41E+06 2.61E+C6 2.35E+06 2.SSE+06 2.45E+06 3.55E+06 2 a;-111 4.03E+05 2.32t*05 2.51E+05 2.53E+05 2.31t+05 3.39E+05 4.03E+04 2.32E+04 2.51E+04 2.c3E+C4 2 31E+04 3.39E+C4 50-122 n.0ct+04 c.276+C4 o.SSE+C4 6.31E+04 5s24E+04 7.73E+J4 6.33E+c5 S.31E+05 5.57E+05 5.35E+C5 4.4cE*05 6.54E+05 l
t 58-124 2.01E+07 2.2EE+uT 2.07E+C7 2.27E+G7 1.9EE+07 2.71E+07 2.1LE+06 1.d6!+06 1.67E+06 .1.90E+06 1.6&E+06 2.25E+C6 9.31E+C5
- 1. .u 1 E + L 7 7. 3 9 t. +.. 0 6o. 47t+06 a . U,3, E +..r. 0 6 o . L,S, E ,.n
+06 9.91E+06 9. 5, 2, E
- 0, 5 6.94E+05 6. 0,9 E + 0 5 7. 5,5 E, + C 5 6,,. 4 3,E + 0 ,,ygg.
n .ng , 75 ,e3 5 g 5e.127.
.- . _,..- . -. w..r, , , s ,3,.3. 4, ,, g ;,ns,.,g 7, 3..ng 3,
APPENDIX A Tabic 2.3 (Continued) Sh ut 2 ef 3
..................... 5g InnIms ..................
.................. ,(NEEM / TEAR PE4 UCI/NL) ************** .................... 5HCR ELINE
- u , .
NUCLICE SCNE GI THveC10 (HREM/ FEAR PER UCI/5QU4RE CENTINETER) *********.
18 L!vE4 SKIk 804E GI THft0!D T8 LIVER SKIN
~
TE-127 7.64c+C4 5.176+04 4.9;E+C4 5.77t+04 4.93E+04 6.53E+G4 7.74E*J3 5.1CE+03 4.92E+G3 5.69E+03 4.77E*03 6.50E+03 TE127M 6.91E+04 1.33E+04 3.45E+C4 3.52E+04 1.26E+04 9.39E+04 1.31E*04 2.54E+03 6.60E+03 7.21E+G3 2.44E+03 1.86E+04 TE-129 8.est+C5 6.12E+05 5.5tE+05 6.69E+c5 5.6CE+C5 B.33E+C5 c.52E*04 5.d7E+04 5.43E+04 6.50E+04 5.37E*04 8.28E+04 TE129M 4.72E*C5 3.23E+05 2.94E+05 3.71E+05 3 02E+05 5.03E+05 4 69E+04 3.09E+C4 ?.93E+04 3.71E+04 2.5EE+04 5.33E+C4.l' TE-131 o.79E+C6 . 21E+06 4.37E+C6 4.99E+06 4.13E+06 6.11E+06 6.4?E*05 3.94E+05 +.16E+05 4.71E+05 3.8sE+C5 5.78t+05 TE131M. 2.06E*C7. 1.53E*C7 1.39E+07 1.7GE+07 1.45E+07 2.12t+07 1.E4E+06 1.35E+06 .1.23E+G6 1.51E+C6 _1.2!Et06__1.89E+C6-_,
TE-132 4.27E*Cs 1.92E*J6 2.54E+06 2.63E+36 2.G4E+0e 3.32E+C6 4.55E+L5 1.93E+05 2.6dE+C5 2.23E+05 2.12 E
- 0 5 3.6CE+C5 I-129 2.25E+C5 4.$4E+04 1.19E*J5 1.15E+05 4.75E+04 2.4?E+05 5.02E+04 1.075+04 2.67E+C4 2.57E+C4 1.05E+04 5.7CE+C4 _.
I-130 3.0iE*C7 2.33E+07 2.0CE+C7 2.50E+w7 2.14E+07 3. 0 C E + 0 7 2.5LE+06 2.17E*06 1.86E+C6 2.32E+06 1.99E+06 2.86E+06 .
1-131 6.22E*C6 3.93E*C6 3.92E+C6 4.54E+06 3.77E+C6 5.47E+0c 6.15E+05 3.57E+05. 3.35E+05 4.49E+C5 3.72E+05 .5.41E+C5 . _,
I-132 3.23E+07 2.45E+07 2.16E+G7 2.oEE+07 2.29E+07 3.32E*07 2 91E+06 2.20E+G6 1.93E+06 2.41E+C6 2.06E+06 2.99E+C6 i
_ I-133_ _o.96E+06 6.90!+C6 ,5.59E+06 7.13E+uo 6.16E+06. J.69E+06 8.44E+05 6.45E+35. 5.54E+05 _!.75E+05 5.79E+05. 8.17E+C5 \
I-134 3.o7E+C7 2.d4E+07 2.49E+07 3.11E+07 2.65E+07 3.u9E*J7 3.22E+06 2.46E+06 2.15E+06 2.71E+06 2.32E+06 3.4CE+06 '.
I-135 2.19E+07 1.95E+07 1.75E+07 1.9di+07 1.67E+07 2.33E+07 1.7BE+C6 1 57E+06 1.41E+06. 1.5BE+06 1.35E*06 1.39E+C6.... ..
- E133M 6.05E+C5 2.3EE+05 3.55E+05 3.71E+05 2.61E+05 5.27E+05 3.09E+04 2.01E+04 4.65E+04 4.77E+04 3.0$!+04 7.71E+04 IE-133 s.52E+05 2.53E+05 4.84E+C5 4.24E+05 2.74E+05 5.73E+05 1.11E+05 3.17E+04 6.2SE+04 5.572+04 3.39E+04 5.27E+04 _ ,
EE135M 6.41E+C6 4.94E+06 4.15E+Co 5.04E+06 4.33E+C6 6.03E+06 6.21E+05 4.75E+05 4.01E+05 4.87E+05 4.17E+05 5.90E+05 XE-135 4.54E+C6 2.25E+06- 2.76E+0S 3.02E+06 2.4CL+06 3.63E+06 4 59E+05 2.29E+05 2.7?E+05 3.04E+05 _2.41E+05. 3.67!+C5 C5-134 2.22E+G7 1.o7E+07 1.43E+07 1.31E+G7 1.55E+07 2.26E+07 2.04E+Go 1.54E+06 1.32E+06 1.67E+06 1.43E+06 2.08E+C6 C5-135 0.00E+C0 C.00E+C0 0.00E+00 C.GOE*00 0.00E+00 0.0CE+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 C.CCE+00 0.0CE+00 C5-136 3.1CE+07 2.26E+07 2.03E+07 2.55E+07 2.152+07 3.21E+07 2.77E+06 2.0CE+06 1.81E+C6 2.26E+C6 1.91E+06 2.85E+C6 C5-137 0.0CE+00 0.COE+00 0.00E+00 0.0CE*00 0.00E+CC 0.00E+00 C.00E+00 0.UCE+00 0.00E+00 0.CCE+00 0.0CE+00 0.00E+00 C5-135 3.29E+0? 3.C3E+07 2.66E+07 2.98E+07 2.56E+67 3.46E+07 2.62E+C6 2.37E+06 2.23E+06 2.35E+06 2.02E+06 2.74E+C6 3 413 7M ___ 6.5 6 E+ C 6__6 9 5 E+ C 6 _ 5.4 S E + C 6 _6. 9 2E + 0 6 _ 5. 91 E +0 6.. 8.5 9 E + 0 6 _ . 8. 01 E + 05. c.U2E!05_.5.12E+G5_ 6.475t05__5 54!?05_ 8.04E+C5 ___ __
LJ 34-139 7.49E+C5 3.44E+05 4.73E+05 4.6cE+05 3.c0E+05 5.55E+05 7.61E+04 3.3EE+04 4.75E+C4 4.67E+C4 '.57E+04 5.62E+04 I" 3A-140 2.29E+C6_ 1 6CE+G6 1.46E+36. 1.73E+06 1.4bE+06 2.10E+06 2.29E+05 1.56E+05 1.46E+05 1.71E+05 1.42E+05 2.13E+C5 4A-141 1.31E+C7 8.90E+06 8.96E+06 1. 0 2 E + 0 7 8.49C+0i 1.22E+07 1.21E+CS 7.97E+05 8.15E+05 9.26E+05 7.70E+05 1.12E+C6 34-142 1.51E+C7 1 11E+07 1.C2E+07 1.24E+07 1.04E+07 1.54E+07 1.34E+06 9.3EE+05 9.03E+05 1.10E+06 9.17E+05 1.36E+C6 LA-140 3.2CE+C7 2.91E+07 2.73E+07 2.eEE+07 2.4oE+07 3.31E+C7 2.6CE+06 2.32E+06 2.18E+06 2.32E+06 1.9EE+06 2.67E+C6 EA-142. 3.76E+C7 3.20E+07 3.72E+J7. 3.47E+07 3.10E+07. 4.10E+07 2.75E+06 2.73E+06 2.64E+06 2.53E+C5 2.52E+06_ 3.0CE+06 CE-141 1.59E+C6 5.94E+05 9.70E*05 9.01E+05 6.7:E+05 1.09E+06 1.69E+G5 6.2CE+04 1.02E+05 9.52E+04 7.07E+04 1.16E+C5 CE-143 4.54E+G6 2.04E+Co 2.79E+06 3.22E+06 2.60E+0e 4.00E+06 4.66E+05 2.6iE+05 2.83E+05 3.24E+05 2.57E+05 4.07E+05 CE-144 4.1EE+C5 1.42E+05 2.51E+05 2.26E+05 1.6?E+05 2.31E+G5 4.64E+04 1.55E+04 2.70E+04 2.50E+C4 1.76E+04 3.18E+04 Pa-143 1.26E-01 9.3dE-G2 6.0CE-02 1.03E-01 a.3;E-02 1.3CE-01 1.15E-C2 8.6CE-03. 7.33E-03 9.45E-03 3.09E-03 1.19E-02 PR-1=4 4.40E*05 4.24E+05 3.74E+05 3.97E+05 3.5CE+05 4.75E+05 3.40E+04 3.24E+04 2.57E+G4 3.10E+C4 2.72E+04 3.71E+04 PR144M 1.42E+C5 3. J 2 E + C 4 _7.19 E t 0 4_ 6. i S E t 0 4 _3. 2 3 E + 0 4 _1. 2 5 E t 0 5 2.2SE+04 _5.33E+03_,_1.15Et04__1.12Et04_).17Et03__2.C6E+04______
NO-147 1.34E+06 2.33E+C6 1.44E+06 1. 3 72 + 0 e 1.25E+04 1.93E+06 2.47E+05 1.35E+C5 1.50E+05 1.62E+05 1.27E+05 2.03E+C5 PM-147 7.ESE+C1 2.76E+01 4.92E+01 .4.26E+01 -3.23E+01 4.93E+01 d.17E+00 2.92Et00 5.11!?GO. 4.43E+00 3.36E+03 5 17E+C0 PM-149 1.96E+C5 1.12E+G5 1.23E+C5 1.39E+05 1.13E+05 1.o9E+05 1.98E+04 1.11E+04 1.22E+C4 1.33E+04 1.12E+04 1.67E+C4 5M-147 0.00E+C0 0.00E+GO 0.CCE+00 0.00E+00 0.0CE+CC 0.00E+C0 0.00E+00 0.0CE+00 .0.00E+00 0.00E+00 0.0CE+00 0.0CE+00 SM-151 1.69E+01 2.20E+00 5.oEE+00 1.33E+C1 1.61E+0C 6.76E+01 7.60E+00 1.04E+00 2.56E+0C 6.24E+00 7.22E-G1 3.55E+C1 SM-153 _ 1.25E+C6 _3.59Etu5__7.21E+C5__e.33Et05,_.4.25E+05,_8.08Et05.,_ 1.57E+05_.4.71Et04_ 8.7sE+C4 __7.83E+04 5.07E+04 1.04E+05 EU-155 1.35E+C6 4.23E+05 7.9EE+05 6.81E+05 4.7EE+05 6.21E+03 1.54E+05 4.82E+04 6.90E+04 7.73E+C4 5.35E+C4 9.49E+C4 x TA-152 2.42E+05 1.90Et05, 1.EDEt05_ 2.04E+06 1.6dE*05 2.44E+05 1.94E+06 1.41E+06 1.45E+C6 1.63E+06 1.35E+06 1.96!+C6-
@ w-137 7.25E+Co 5.09E+C6 4.57E+06 5.55E+06 4.68E+C6 6.E1E+06 6.99E+05 4.84E+C5~ 4.39E+05 5.30E+05 ~ .45E+05 4 6.52E+05 78-210 3.69E+04 9.75E+03 1.71E+04 1.76t+04 9.10E+03 3.27E+04 5.31E+03 1.46E+03 2.42E+03 3.05E+03 1.25E+03 1.43E+04 i 78-212 2.89E+C6 1.26E+06 '1.72E+36 1.76E+06' 1.36E+06 2.13E+06 2.99E+05 1.29E+05 1.78E+05 '1.83E+05 "1.40E+05' 2.25E+35 2
" _75-214 -_ 4.29E+C6__2.39E*06 _2.65E+06 2.95Et06__.2.39E+06__3.55Et06 ___4.32Et05_ 2.39Et05 ,_2.66Et05__2.96Et01__2,39E+05___3.6)Et05 4I-212 2.59E+C6 2.03E+C6 1.89E+06 2.22E+06 1.90E+06 2.69E+36 2.25E+05 1.73E+05 1.61E+05 1.92E+C5 1.63E+05 2.36E+05
- a SI-214 2.1CE+07 1.39E+07 1.69E+C7 1.37E+07 1.62E+07 2.23E+07 1.71E+06 1.51E+06 1.35E+C6 1.51E+06 1.31E+C6 1.31E+06 0 70-212 0.00E+C0 0.00E+00 0.COE+C0 0.0CE+00 0.0CZ+CC 0.00E+C0 0.00E+00 0.00E+00" 0.00E+00 0.00!+C0 0.0CE+C0' O.0CE+C0
'~"
PC-214 1.54E+03 1.14E+03_ 9.75E+02 1.275+03 1.09E+03 1.62E+03 1.39E+02 1.03E+02. 8.34Et01 1.155?02 _9.85E+01_ 1.46E+C2_____,90-216 0.00E+C0 C.0C!+00 C.CCZ+C0 0.00t+00 0.00E+0C 0.00t+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+C0 0.0CE+00 0.00E+0C
_80-218 0.GOE+C0 C.0CE+00_0.0CE+00 _0.00E+00 0.0CE+CC 0.00E+00 0.00E+00 0 0CE+00 0.CCE+00 0.00Et00 _f,0CE+00_ 0.00E+C0__ ___
s k
L-____ -- - ---_-_A
APPENDIX A Teble 2.3 (Continued) Sheet's\ -3 eeeeeeeeeee.e.ee..eee 5W IMM 1NG eeeeeeeeeeeeeeeeee eseeeeeeeeeeeeeeeeee 5HCRELINE ceccaccc800000c % + '
.e+....eee.e.e.eee. (NaEM/ TEAR PER UCI/NL) seeeeeeeeeeeee esseeeee (HAEM / FEAR PER UCI/5:UARE CENTINETEa) ,eseceosaq
'suCLICE 80NE GI TNTROID TS LIVER SKIN 8ONE GI THYROID TB ,
LIVER' SKIN . . ,o
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1 87E Q5~ i.~92E+04 1.13E+05 1.21E+05 9.45E+04 1.45E+05 1.90E+04 9.04E+03 1.15E+0I ~1.22E+04 9.58E+03 1.49t+04 * *
' 'a 'A -2 2 f I 6.26E+04 9.43E+04 1.41E+04 5.94E+03 8.41E+03. 8.45E+03 ,6.41E+03 _1.05E+04 sA-226 1.37E+05 _5.79E+C4..d.19Et04_ 8.21E+04 7.89E-05 d.6tE-05 1.74E-05 4.19E-04 3.68E-07 7.89E-03 -:
RA-228 4C-228 6.53E-G5 9.39E-05 1.88E-C5 4.53E-04 1.32E+07, 9.95E*06 5.99E+06 _1.10E+07. 9.3CE+06 3.9EE-07 8.53c-G3 1.37E+07 1.17E+06- d.65E+05 7.56E+05.;9.64E+G5.,8.14E+05_ 1 23E+06 .,
k.
4.75E+03 1.67E+03 2.74E+03 2.95E+C3 i.84E+03 8 8EE+03 ,
e.33E+04 1.54E+04 2.56E+04 2.41E+04 1.74E+04 3.33E+04 in-228 3.79E+03_ 2.56E103 _4,78Et03 _4.d3E+03__3 07E+03 ,1.00E+04 1.11 E +0 3. 3.5 3E+02_5.4 4 E+02. 5.92 E t0 2._3.3 P Et02 5 3 6 E t03
_TH-23C_
3 91E+C3 1.20E*03 2.03E+03 2.21E+03 1.23E+03 6.31E*03 5.93E+02 1.73E+02 2.53E+02 6.10E*G2 1.45E+02 5.44E+03 TM-232 2.14E+04 6.7CE+03 1.23E+04. 1.11E+04_ 7.33E+03._1 94E+04 ._
TM-234 1.90E+C5 0.00E+04 1.1CE+05 9.53E+04 6.63E+04 1.12E+05 PA-234 ~ ~2.89E 4C7'2.07E+C7 1.92E407 2.34E+07 1.98E+07' 2.93E+07 2.61E+06 1.83E+06 1.72E+06 2.10E+06 1.77E+06 2.69E+06-4.05E+03 5.71E+02 1.46E+02. 1.85E+02. 7 43E+02 1 00E+02 _7 34E+03._._ ,
l u-234 2.77E+03_ 8.30E+02_ 1.36E+03 1.SOE+03 4.36E+02 1.97E+02 5.91E+03 3.32E+02 8.41E+01 7.05E+01 5.46E+02 2.97E+01 6.C6E*03-t U-238 9.o?E+C2 2.47E+02 3.edE+02 6.0ZE+02 4.93E+05 4.12E+C5 5.54E+05 4.69E+C5 .7 45E+C5__....
6.5CE+05 j .NP-23d 7.5Ct+Cd 5.7Js+0e 4.77:+Je c.3fE+C4 5.43E+0e 8.12E+0A 3.59E+05 1.45E+05 2.22E+05 2.13E+05 1.62E+05 2.9CE+C5
! WP-239 3.44E+0e 1.40E+06 2.14E+Co 2.J2t+D6 1.57t+0c 2.43E+06 4.77E+02 1.42E+02 7.02E+C1 7.97E+C2 2.54E+01 E.55E+C3 PJ-233 9.79E*02 2.32E+02 3.16E+C2 1.uCE+J3 1.67E+02 8.46E+03 2.33E+02 a.55E+01 9.52E+01 3.6CE+C2 5.44E+01 3.32E+03 .
PU-239 1.39E+03 4.51E+C2 7.9EE+02 9.42E+02 5.C5E+02 3.37E+03 4.65E+02 1.36E+02 7.17E+01 7.64E+02 2.69E+01 8.14E+C3 _. ..
PU-240 1.01E+03 2.33E+02 3.34E+02 .9.9CE+02 1.73E+02 6.10E+03 0.00E+00 0.DCE+00 0.0CE+00 '
pu-241 0.00E+C0 0.00E+00 0.00E+00 0.0CE+00 C.00E+C0 0.00E+00 0.00E+00 0.CCE+00 .0.00E+GO 6.40E+03 3.6dE+G2 6.23E+01. 5.81Et01. 6.03E+02 _.2.22E9C1._6.41EtC3
_PU-242 __. 8.25Et02 1.93E+C2 .2.83E+02.. 7.96E+02 .1.52E+02 6.40E+G4 1.61E+04 3.11E+04 3.16E+04 1.79E+04 5.77E+C4 5.01E+05 1.43E+C5 2.472+05 2.37E+05 1.42E+05 3.12E+05 AM-241 3.32E+04 1.11E+04 2.07E+04 1.80E+C4._1.29E+04 2.97E+C4 ... . . .
AM-242 3.0$E+C5 1.04E+05 1.95t+05 1.0ZE+C5 1.21E+05 1.96E+05 1.37E+05 4.16E+04 7.49E+04 6.79E+04 4.42E+C4 9 3CE+04 AM-243 1.22E+06 3.71E+05 6.7CE+05 3.97E+05 3.96E+05 7.28E+05 6.062+02 2.02E+02 7.14E+01 9.05C+02 _2.57E+01 9.DCE+03 _.
1.05E+03 2.95E+02 2.97E+02 1.14E+03 1.56t+02 9.49E+03 Cn-242 2.63E+C5 1.G9E+05 1.64E+05 1.62E+05 1.22E+05 2.33E+C5 CM-243 2.57E+C6 1.06E+06 1.59E+0e 1. 5 3 E.+ C o 1.1JE+C6 1.85E+U6 5.22E+02 1. tee +02 .4.96E+0i .8.07E.02__1.34E+0i_ 8.15E+03.._..
_CM-244_. 6.91E+02..,2.00E+02._ 1.25E+02 9.01E+02 5.13E+01 .E.47E+03 !
b .a . . .
p
- Dose Factors taken from Kocher, D. C., " Dose-Rate Conversion Factors for External Expo'sure t'o Phot 6n and Electron Radiation from Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities," Health Physics, Volume 38, Number 4, April 1980. ._. _ ._.. . . . . . . . . _ _
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. ./ .. . APPENDIX A PAGE: NO.* TITLE:
.., '4 of 4 RAP 2 9' IMPLETE'1TATION OF RETS SUR'.'EILI.ANCE REQUIREElTS 4.11.1.2, 4.11.3.1 App. 1 DATE: 10/5/83 AND 4.11.4 FOR SEQUCYA!! Ni'C'.E.*a PIrrr
(\.
e a
t COMRAENTS STEP KEY ENTHY KEY CODE CO'Sws e.g..
TP NEY fNTRY REY COCE til *L6LB at J.
Ili i:Cl 35 46 172 STCE 35 15 IIG sLEL4 21 04 R/S 51 -t%
117 RCLE 3G 46 173 174 sL6LC 21 13 yc lit 2 e2 ' f ' il". ,
175 1 01 119 3 83 d* f' ITG 5 85 120 xsY? 16-33 . s,;
121 CICO 22 && *
!?7 $101 35 46 '
122 SCLI 3G 45 ; 178 RCLI 36 45
~
- UV I23 ::s6+ 15-43 172 4g 42 ISO 8 '06 124 C;03 22 83 181 0 90 125 RCL E 36 46 IS2 1 01 826 CS?& -43 96 127 FIX -11 183 '52 63 184 x -35 122 FF X -it 129 :SP2 -63 02 185 1921 16 26 46 133 RCLI si 45 tRG RCLE 36 45 so? -62 131 RCL0 3G 00 . 4 188 8 6d 132 2 ' -35 5G 133 PR1X - -14 !$9 Os 134 RCLI 3G 45 190 1*l 02 135 C572 -63 92 1.*l 2 2. . 03 192 x ~35 ~~
136 SCI ~12
%4 193 e. -55 137 FR1X I 194 2 02 j IIS FCLE 36 4i 08
!?2 2 92 195 1
's' -148 2 82 196 ST01 35 46 X=Y' 16-33 197 RJ -31 141 142 CTCO 22 ed 198 F.CL I 3 45 '
199 ~52 143 sLfL3 21 03 8
40 90 144 1521 JG 26 46 290 201 2 92 145 C104 22 04 146 15Z1 16 26 4G 282 10 01 147 CT04 ' 22 e4 203 Q Os pes 51 284 x -35 148 205 * -55 149 eLFLJ 21 66 I59 RCLG 36 96 206 1$22 IG 26 46 158 1/X 52 , 207 RCLI 3G 45
152 i el 298 .g -f2 .
EEX -23 20) 0 80 853 154 4 84 210 3 03 155 + -24 ./ 211 Wl 95
.i,*;{'J**-'.< . 156 dst 9 -G3 09 212 5 2., 06
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- 157 PR1x -14 213 *n -35
+ -55 .
158 $PC 1G-11 214 215 RCLE 3G is *
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) 159 CSP 2 160 RCLE 36 !$ 286 s -24 .
stC 161 flX -18 287 16-18
- i. '162 0$f3 -63 06 288 (Rix . -14
' lC3 FR1X -14 219 Ris 51 164 SCI -12 865 DSP2 -63 02
. g.i?,, ~a _ p ,, 166 SPC 16-il , Le.. .
A < - 167 $rc 16-18 '
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4
. TENNESSEE VALLEY- AUTHORITY Sequoyah Nuclear Plant
~
P. O. Box 2000 Soddy-Daisy, Tennessee 37379 SEP 141984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the August 1984 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region II Director, Office of Management Nuclear Regulatory Consission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta Street Washington, DC 20555 (2 copies)
Suite 3100 Atlanta, GA 30323 (1 copy) INPO Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Entorcement Atlanta, GA 30339 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 P. O. Box 355 Pittsburgh, PA 15230 (1 copy)
St *M
.b An Equal Opportunity Employer