ML20077A861
| ML20077A861 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/03/1983 |
| From: | Dupree D, Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8307220474 | |
| Download: ML20077A861 (45) | |
Text
{{#Wiki_filter:_ TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MAY 1, 1983 - MAY 31, 1983 UNIT 1 DOCKET NUMBER 50-327-LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE, NUMBER DPR-79 Submitted By: /Q Power Plant Superintendent 0307220474 830603 PDR ADOCK 05000327 R PDR i
TABLE OF CONTENTS Operations Summary . . . . . . .. .. . . . . . . . . . . . . . . I Significant Operational Events . . . . . . . . . . . . . . . . . 1-3 PORV's and Safety Valves Summary-. . . . . . . . . . . . . . . . 4 Licensee Events and Special Reports . . . . . . . . . . . . . . 4-6 Offsite Dose Calculation Manual Changes .. . . . . . . . . . . 6 Operating. Data Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . 7-9
' Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . 10-12.
Plant Maintenance Summary . . . . .. . . . . . . . . . . . . . 13-20 Appendix A . .-. . . . . . . . . . . . . . . . . . . . . . . . . 21-42 l I I t i l l
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Oparstions Summary May, 1983 The following summary describes the significant operational activities for the month of May. In support of this summary, a chronological log of significant events is included in this report. Unit 1 Unit I was critical for 737.83 hours, produced 846,100 MWH (gross),
'resulting'in an average hourly' gross load of 1,152,725 kW during the month. -
There are 171.92 full power days estimated remaining until the end of cycle 2 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached December 20, 1983. The capacity factor for the month was-97.8 percent. There was one reactor scram, no manual shutdowns, and no power reductions during Hay. Unit 2 Unit 2 was critical for 744 hours, produced 860,480 MWH (gross), resulting in an average hourly gross load of 1,156,559 kW during the month.
-There are 47.29 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached July 26, 1983. The refueling outage is scheduled to begin on August 5,- 1983. The capacity factor for the month was 99.4 percent.
There were no reactor scrams, no manual shutdowns, and no power reductions during May. Significant Operational Events Unit 1 Date Time Event 05/01/83 0001 Reactor in mode 1 at 100% power pro-ducing 1190 MWe. 05/03/83 1105 1A1 water box drained for tube leak testing. Reactor at 100 % power, producing 1180 MWe. 05/05/83 0506 1A1 water box returned to service. Reactor at 100% power producing 1190 MWe. Significant Operational Events Unit 1 (Continued) Date Time Event 05/29/83 2155' Reactor tripped due to a procedure error in TI-52 'Special Instruction for Removing / Returning, the SSPS from/to Service'. 05/30/83 0405 Reactor taken critical. 0755 Unit tied on-line. 0850 Reactor at 30% power and holding for the steam generator chemistry. 2300 Began power ascension. 05/31/83 0555 Reactor at 100% reactor power producing 1170 MWe. 2359 Reactor in Mode 1 at 100% power producing 1180 MWe. Unit 2 Date Time Event 05/01/83 0001 Reactor in Mode 1 at 98% power producing 1172 MWe. Control Rod D-8 inoperable and #3 governor valve closed. 05/09/83 1740 A primary to secondary tube leak in
#3 steam generator is indicated.
05/20/83 0450 C-2 MSR HP stage taken out of service for maintenance. Reactor at 98% power producing 1160 MWe. 1330 2B-1 water box taken out of service for tube leak testing. Reactor at 98% power producing 1153 MWe. 1721 2B-1 Water box returned to service. Reactor at 98% power producing 1160 MWe.
._ __ . _ .- . . ~ . _ --- _ _ . , . - ___ _ _ .
Significsnt 0parationtl Events Unit 2 (Continued) Date' Time Event 05/21/83 0440- 2B-2 water box taken out of service
-for tube leak testing. Reactor at 98% power producing 1153 MWe. I 1010 2B-2 water box returned to service.
Reactor at 98% power producing . 1160 MWe. l l 1305 C2 MSR HP stage returned to service. Reactor at 98% power producing 1165 MWe. 1326 C-2 MSR removed from service. Reactor at 98% power producing 1160 MWe. 1600 C-2 MSR returned to service. Reactor at 98% power producing 1165 MWe. ; i 05/22/83 1625 C-2 MSR removed from service. Reactor at 98% power producing 1160 MWe. 1925 C-2 MSR returned to service. Reactor at 98% power producing 1165 MWe. 05/31/83 2359 Reactor in Mode 1 at 98% power producing 1165 MWe. Control Rod D-8 inoperable and #3 governor valve is closed. i j i i t i
PORV'S and Stfety Valves Summary No PORV's or safety valves were challenged during the month. Licensee Events and Special Reports The folloring Licensee Event Reports (LER's) were sent during May 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
~ Unit 1 LER SUBJECT SQR050327/83055 Bank D movable control assembly was declared inoperable because the rods failed to move when a urgent alarm was received. The 'C' phase reference voltage fuse was found blown.
SQR050327/83056 The inner door to the upper containment airlock (penetration X2B)was discovered inoperable. The latching mechanism had a sheared stud and a failed cam follower bearing allowing the outer door to be open while the inner door was not fully closed. SQR050327/83057 The subcooling margin monitor was declared inoperable due to a power failure affecting the plant process computer. SQR050327/83058 The turbine building sump radiation monitor
. 0-RM-90-212 was declared inoperable when the low flow switch failed to actuate during the performance of SI-476. Debris was found blocking the switch.
SQR050327/83063 While attempting to reset PORV 1-PCV-68-340A, it failed to open due to a failed coil in ASCO solenoid model LB 831654. . SQR0-50-327/83065 EGTS Train A room cooler was declared inoperable - during the performance of SI-166.21 due to a short in ASCO solenoid valve coil on 2-FSV-67-336. SQRO-50-327/83066 While changing one UH1 level switch and recali-brating three to new set points, three of the four were found out of tolerance (1-LS-87-21, -22, -23) due to instrument drift of the Barton 288A level switch. SQRO-50-327/83067 Start bus IB was declared inoperable due to a Phase-to-Phase fault caused by a breakdown of insulation on Westinghouse Model EN-265 Bus. The D/G's were not proven operable within one hour as required by the STS. Lierneee Evznts and Special Reports Unit 1 (Continued) LER SUBJECT
, SQRO-50-327/83070 1A-A D/G was delcared inoperable due to an oil cooler failure and cylinder head leak.
SQRO-50-327-83071 The waste gas disposal system oxygen analyzer 0-02AN-43-5000 was declared inoperable during the performance of SI-243 due to instrument drift. Unit 2 SQR0-50-328/83059 The rod C-5 indicator was delcared inoperable due to being misaligned by more than 12 steps. SQRO-50-328/83060 2-LCV-3-156 failed to open on demand because the metering orifice in the pneumatic relay was the wrong size. SQR0-50-328/83061 S/G #2 pressure indicator 2-P1-1-9A failed low because the Foxboro Model 66BC-OH current-to-current module failed due to end of normal life of the transistors. SQR0-50-328/83062 During increased frequency performance of SI-196,
. 2-LS-87-21, -22, -24 were found out of tolerance due to instrument drift.
! SQRO-50-328/83064 AFW valve 2-LCV-3-148 failed to open on demand i because of faculty voltage to the current l circuit board in the Beckman Model 8813-2098-0200 I controller. l SQRO-50-328/83068 Number 2 cold leg accumulator was overfilled and _ t overpressurized causing the RWST to drop below its lower limits. The SI pump was not shut down due to personnel error. SQRO-50-328/83069 The RCS subcooling margin monitor was declared inoperable due to loss of plant process computer due to a power spike. l SQRO-50-328/83072 The remote shutdown S/G No. I pressure indicator was declared inoperable due to failing high. The oscillator in the GE current isolator 2-PM-1-1C was grounded due to a loose connection causing the output to read high. l
Licansen Events and Spscial Reports (Continued) Unit 2 LER SUBJECT-SQRO-50-328/83073 Shield building exhaust gaseous effluent rad monitor 0-RM-90-100 was declared inoperable during the performance of SI-205.2 because the required output voltage levels could not be obtained due to a weak photomultiplier tube. SQR0-50-328/83074 The RCS subcooling margin monitor was declared inoperable due to the failure of the plant process computer due to a power interruption. Special-Reports There were no special reports transmitted during the month of May. 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 officially approved by RARC on March 23, 1983. See Appendix A at the end of this report for the approved ODCM changes. i i l l l
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-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT One DATE MAY, 1983 COMPLETED BY S. Lane TELEPHONE (615) 870-6196
. MONTH MAY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)' (MWe-Net) 1 1139 17 1136 2- 1138 18 1137 3 1137 19 1138
-4 1128 20 1138 5 1138 21 1139 6 1139 22 1136-7 1140 23 1135
'8 1140 24 1136 9~ 1140 25 1136 10 1137 26 1136 11 1138 27 1137 12 1136 28 1136 13 1139 29 1135 14 1141 30 272 15 1137 31 987 16 1137 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME SFOUOYAH ONF DATE JUNE 7, 1983
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COMPLETED BY M. Eddines REPORT MONTH N TELEPHONE (615) 870-6196 W 1O
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C yy Licensee y Cause & Corrective No. Date & Oy 8 ]O@ Event g *, gea Action to y 2e 2 5y* Report !. gj 8,] Prevent Recurrence 5" $5$ N" " e 18 810529 F 10.0 n 3 Instrument Mechanic Proceedure Error
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P/ 2 3 4 4 F: Forced Reason: Method: S: Scheduled Exhibit G-Instructions A-Equipment Failure (Explain) 1-Manual for Pr'paration e of Data B-Maintenance or Test s 2-Manual Scram. Entry Sheets for Licensee C-Refueling gT 3-Automatic Scram.' Event Report (LER) File (NUREG-D-Regulatory Restrictied/ 4-Cont. of Existing' 0161) E-Operator Training & Olcecse. Examination .,0ntage
.F-Administrative -l' s
' 5-Reduction \
G-Operational Error (Explain) 4
.9-Other' s 5 (9/77) H-Other (Explain)
Exhibit I-Same Source
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. . I OPERATING DATA REPORT l DOCKET NO. 50-327 DATE JUNE 6, 1983 COMPLETED BY M G EDDINGS TELEPHONE (615)S70-6248 OPERATING STATUS- ^
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- 1. UNIT NAME: SEQUOYAp' NUCLEAR PLANT, UNIT' 1. NOTES:
- 2. REPORT (PERIOD: M AX 19s3
- 3. LICENSED THERMAC'PdWER(MWT): 3411.0 #
- 4. NAME* LATE RATING'(GROSS MWE): 1220.6
5.fDESIGN ELECTRICAL RATING (NET MWE):' 1148.0' 6.-MAXIMUM DEPENDABIEf CAPACITY'(GROSS MWE): , 3163.0 j 7. ' MAXIMUK DEPEND ABLE CAPACITY (NET MWE): . 113E.0
- 8. IF? CHANGES OCCUR IL CAPACIT,Y RATINGS (ITEMS,NUMSEf4S
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_ 3 THROUGH 7)SINCE LAsr*M9 RTs GIVE REASON %:~___ls.______ _______________.___3.______
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- 9. POWER LEVEL TO WHICH R ES T RIC rid r I F ANY(NET MWE): _______
- 10. 5E 50 5' hR'RE5iR5Ciib55 iF~555$((((((((((((['[~_'~_(([.'[~ _ _
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS ~IN' REPORTING PERIOD 744.00 i,3423.00 16800.00 12 ,rNUM9ER OF HOURS REACTOR WAS CRITICAL 737.83. 3078.68 10614.38
-13. REACTOR RESERVE SHUTD0dN HOURS 0.00 t f 0.00 0.00
- 14. H90RS GENERATOR,0N-LINE 734.00 -
2995.70 10315.20 15.' UNIT RESERVE'SHUTDQWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY, GENERATED (MWH) 2454749.35 n.9666454.71 32949196.71
- 17. GROSSL ELECTRIC AL ENIRGY GEN'. (MWH) 84o100.0i t ' 3336120.00 11093656.00
- 18. NET ELECTRICAL ENFRGY GENERATED'iMWH) 817786.00 3213367.00 10649871.00 719. UNIT SERVICE FACTOR. 98.66 P'- 82.69 61.40 '
- 20. UNIT AVAILABILITY ~ FACTOR 98.66 82.69 61.40
[21. UN!T/t AP ACITY FACTOR (USING MDC NET) 9 7 . 4'* ,, 78.64 56.20 22.~ UNIT: CAPACITY FACTOR (USING DER NET) 95.75 - ', 77.27 55.22
- 23. UNIT FORCED OUTAGE RATE 1. 3 * / / , 5.16 14.50
- 24. SHUTDOWNS SCHEDul,ED OVER NEXT 6 MONTHS (TYPE 7 Cf?ff'AND DURATION OF EACH):
_____________.___,,___________________________-.11 __________________.
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_aa.Oc__,_________g?______________________.___%._____f________________ ~ >$5. IF SHUT 0JWQ7AT END' 0F fREPORT PERIOD, ESTIMW?ED DATE OF_STARTUP: __ _________________g________L________:____t_____________________ i-r - ~,
. / ; s a y r - .NbTErTHAT "RI THE YR.-TO-pATE AND -
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CURULATIVE VACUES.HAVE ^ BEdN ,/UfDATED.
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AVERAGE DAILY UNIT POWER LEVEL
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i s 'j i' % s DOCKET NO. 50-328 s UNIT TWO
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.s i DATE 6-03-83
'N COMPLETED BY David Dupree TELEPHONE (615) 870-6543 HONTH Mgr DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) 1 1123 17 1120 2 1118 18 1118 3 1119 19 1118 4 111R 20 1113 5't
- 1118 21 51115
'6 1120 22 'll19 l' 7 1120 23 1120
,a s 8- , _: 1!20 24 1117
-}.- S9 1120 25 1115 q
f! < 10 1 1121 26 1115 1 _s \ 1, 1,1 1123 27 1116
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% 12 1121 28 1119
.[ \l3 1121 29 1118 t"14 1121 30 1118 15' 1121 31 III9 Q .g. 16 1119 i INSTRU('TIONS s On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME SEQUOYAH TWO DATE 6-6-83 . COMPLETED BY David Dupree l REPORT MONTH MAY TELEPHONE (615) 870-6343 W C
- gg % ep" Licensee p. Cause & Corrective No. Date 8, O$ ]t2 Event 8 5% 8% Action to R 2j @ fy* Report # g? g] Prevent Recurrence 5" $@$ N* 8" None 1 2 3 4 F: Forced Reason: Method:
S: Scheduled Exhibit G-Instructions A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161) E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source i
OPERATING DATA REPORT DOCKET NO. 50-328 DATE 6-7-83 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6543
-OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORT PERIOD: MAY 1-MAY 31,1983
- 3. LICENSED THERMAL POWER (MWT): 3411.0
- 4. NAMEPLATE RATING (GROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM. DEPENDABLE CAPACITY (GROSS MWE): 1163.0 7.-MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1128.0 8.-IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3.THROUGH 7)SINCE LAST REPORTS GIVE REASONS:____.. _____ l
________. _._..______ ___________ .. _ ._______ _______. l
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- 10. REASONS FOR RESTRICTIONSrIF ANY:_______________________
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.00 3623.00 8760.00 12.. NUMBER 3F HGURS REACTOR WAS CRITICAL 744.00 3610.22 749?.92
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. MOURS GENERATOR ON-LINE- 744.00 3575.40 7382.15
- 15. UNIT RE$ERVE-SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY' GENERATED'(MWH) 2490821.76 11769217.28 23923808.08
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 860480.00 40o341G.00 8145260.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 831527.00 3921415.00 7847705.60
- 19. UNIT SERVICE FACTOR 100.00 98.69 84.27
- 20. UNIT. AVAILABILITY FACTOR 100.00 98.69 84.27
- 21. UNIT C AP ACITY FACTOR (USING MDC NET) 99.08 95.95 79.42 22.-UNIT CAPACITY FACTOR (USING DER NET) 97.36 94.28 78.04
- 23. UNIT FORCED OUTAGE RATE 0.00 1.31 10.00
'24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
32.u,eyqq_0 f gage _39,b,eyjg,Aujtusg_53 19 8,3_, s c h e,d u l e d, ,f o r ,81,,d ags,., , , , , _ , , , , , , , , , , ,
- 25. ii isDiB50s Ii is5 57 iiE5Hi Eisi35- iiiisifiB 5Iii 57 siliiUEi-------
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
Plant Maintenance Summary The following significant maintenance items were completed during the
-month of May 1983:
MECHANICAL MAINTENANCE
- 1. LInstalled a clamp around bonnet and. injected furmanite to repair the bonnet-leak on valve 2-FCV-62-85.
- 2. Resolved 'the hanger problem with the auxiliary boiler steam to CDWE.
- 3. Replaced the shear pin in the latch and repaired the cam follower bearing in the Unit 1 airlock on El. 734.
. 4. Reinstalled flow transmitter 0-FT-27-175 on cooling tower blowdown.
~ 5. Replace the lube oil cooler and power assembly on IA-A diesel generator due to a trip on high crankcase pressure.
Electrical Maintenance 1 , 1. Continued installation of-the Dimension 2000 phone system.
- 2. Continued systematic walk down and inspection of the E-field wiring and made
- - necessary repairs.
!' 3. Completed repairs on the paging system to. fulfill INP0 commitment.
- 4. Replace the motor on unit 2 steam generator blowdown pump 2A.
- 5. -Completed modification to spare RCP motor.
I
- 6. Checked and added oil.to the unit 1 RCP motors.
'7. Made repairs to start bus IB.
l.
- 8. Started repairs to intertie transformer phase A.
! 9. Started inspection and functional testing of the refueling outage support . equipment. l
- 10. Replaced the building heat hot water cire, pump motor B.
- 11. Repaired the filter network on unit I hydrogen recombiner.
j' 12. Performed emergency maintenance on 2A-A diesel generator batteries to
- j. restore them to operable status within the guidelines of the Technical Specifications.
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Plant Maintenance Summary (Continued) Instrument Maintenance
- 1. -Continued monthly calibration surveillance on unit I and 2 UHI level switched. Three of four switches were found out of tolerance on unit I and four of four were found out of tolerance on unit 2. Both units were recalibrated to the newly established setpoint per Tech Spec change.
-This will provide a 5.6" tolerance.
- 2. ;0ak Ridge National Lab online analyzer removal was completed with all temporary connections being returned to normal.
- 3. Implemented the quarterly surveillance testing required for the analog channel functional test of the engineered safety features and reactor trip systems._
- 14. Completed initial calibrations for instruments on the condensate demiueral-izer waste evaporator and turned over to Post Mod Test Group for completion of the Pre-op test. The system was successfully run and an HPD, Inc. factory rep is setting up the auto sequencer at this time.
- 5. ' Started installing a_ flashing red alarm light on each area radiation monitor.
Field Services Group i 1. ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2) The installation of conduit and junction boxes. is continuing on elevation 706 in the auxiliary building. Chipping and preparations for core drilling in the additional equipment building east outer wall (- is underway. Prefabrication and installation of the HVAC ductwork serving
-the PASF area is' continuing. Installation of HVAC equipment serving both-units is.in progress in the PASF area as well. The installation of component cooling piping to the PASF coolers on unit 2 is continuing but the component cooling piping tie-in to the system will require a unit
- outage. Work is continuing to install the post-accident sample tubing in the unit I room. Work is continuing to install the unit 2 post-accident' sample tubing with work concentrating in the unit 2 annulus.
Work is also continuing to fabricate the steel containment vessel penetration plates for the unit 2 post-accident sample tubing to the primary: containment. Tie-in of the demineralized water piping serving the unit 2 PASF equipment to the demineralized water system is complete and insulation of piping is continuing. i
. . = - - ,
Plant Maintentnce Summary (Continued)
- 2. ECN 5096--Common Station Service Transformer-(CSST) "C" Cable pulling to the 161-kV switchyard bays 7 and 14 for CSST "B" is complete. . Termination and lay.down of control cables for the CSST "B" was completed this month as well'. Some miscellaneous electrical work. remains -in the switchyard.
- 3. ECN'5429--Containment Hydrogen Mitigation System (Unit 2)
Installation of conduit and junction boxes in upper containment (excluding the~ ice condenser) is continuing. Fabrication of hanger supports for conduit.in the ice. condenser is complete and intallation in the ice condenser is scheduled in June during a 14-day action statement. Installation of.the hydrogen mitigation system electrical j . equipment and annunciation system in the control and auxiliary buildings 1 is continuing. Fabrication of ccatainment igniter supports is continuing.
- 4. ECN 5009--ERCW Piping Changeout (Units 1 and 2)
Changeout of ERCW piping serving the "B" train penetration room coolers was completed during May and insulation work continues.
~ Installation of piping ~for the unit 2 "A" train penetration room coolers is in progress. Work began during this reporting period to change out the.hypochlorite piping serving the unit 2 containment 2
spray heat exchanger ERCW piping.
- 5. ECN 5645--Steam Generator Blowdown' Heat Exchangers This ECN is to install first and second stage heat exchangers in the steam generator blowdown system for both units 1 and 2. Installation of piping and hangers is continuing for the unit I heat exchangers but completion of -this work has been delayed because of the lack of sufficient hanger design and procurement of materials.. Fabrication and installation
- of piping, hangers, and flow elements on elevation 662 'of unit 2 turbine unit 1 turbine building during May. The heat exchangers for unit 2 are being procured expeditiously and work has begun to install the heat exchanger foundation pads. Fabrication and installation of the unit 2 condensate piping is continuing on elevation 685.
l' 6. ECN 5104--Main Steam Reheater (MSR) Steam Bypass (Unit 1) i The frames are installed for the extension of the three MSR housings (deg houses) around the newly installed MSR steam bypass pipes. i
. Installation of the.MSR housing covers has been delayed until all work associated with the MSR bypass valves is completed. Cable serving the l newly installed MSR bypass valves was completely pulled in.May.
l Installation of nameplates, painting of pipe hangers, cable terminations, and routing of the control air tubing serving all of the bypass valves l remain to be worked.
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Plant Maintenance Summary (Continued)
- 7. ECN 5495--FSG Office Building Power Supply Installation of miscellaneous and communication cables for the building is continuing. Cable trays are being fabricated for installation in the turbine building but fabrication is being delayed due to lack of material.
- 8. ECN 5106--Reactor Vessel Level Indication System (Units 1 and 2)
Work is continuing to install conduit outside the reactor building. The majority of this conduit that can be installed at this time is in place. Work is continuing to install cables for this system outside containment as well.
- 9. ECN 5237--Laundry Room Improvements Some work was performed in May to install the remaining laundry room equipment and associated mechanical systems until material delays stopped work. All equipment has been placed in position except for the wasuing machine and sink which are currently asaiting installatior, of the drain serving this equipment. Remaining work includes extensive modification of the laundry room ventilation system, building a uasonry divider wall, completion of all conduit and power cables serving the facility, and installation of the laundry room chiller. Kork has resumed on the laundry room ventilation cover, conduit, power cable, and chiller installation.
- 10. ECN 5596--Install Batch Neutralization Tank Piping and hanger installation is continuing in the turbine building.
Material procurement will delay completion of this mechanical work until August of this year. Instrumentation and electrical work has not yet begun.
- 11. ECN 5198--Technical Support Center (TSC)
All HVAC system work in the TSC room is complete but completion of this work on the system in the existing relay room is delayed by hanger design. The major work remaining in the TSC room is installation of the fire detection system computer terminals. Work is continuing throughout the spring and summer to install electrical equipment, conduit, and cable for the TSC. t Plent Maintenance Summary (Continued)
- 12. ECN 5642--Add N 2 Regulating Station To Supply N2 To Deaeration Distribu'; ion System Inside Condensate Storage Tanks
.The ni.rogen supply piping to the tanks remain in work between the new liquid nitrogen supply station and the condensate storage tanks.
This piping is installed except for tie-in to the tanks and connection of internal valve cabinet piping. Conduit and cable installation is complete but termination of cables in valve cabinet No. 2 and at the pressure switches on the condensate storage tanks still reamins.
- 13. ECN 2773--Install Radiation Detectors (Unit 2)
Installation of conduit and pulling of cable for the unit 2 reactor building ventilation radiation monitor is in progress and is expected to be. complete early in June with the exception of tie-in to the not yet installed miin control room panel 2-M-30.
- 14. ECN 2923--RHR Lines Radiation Monitors (Unit 21 Conduit installation and cable pulling for thesa mcnitors is nearing.
completion. Remaiaing work includes final cable pulling and terminations at the monitors and at the maia control room ranelt 2-h-30 and 2-M-31 after these panels ac installed.
- 15. ECN 5582--Add N2 Regalating Stations To Supply N2 To Steam Generators This system is charged by the same system that supplies nitrogen to the condensate storage tanks as discussed in this report (ECN 5642.) In addition to the outstanding work described under the ECN 5642 portion of this report, the nitrogen piping tie-in for the unit 2 main steam piping remains to be completed as well as excavation and installation of the unit 1 yard piping.
- 16. ECN 5248--Nitrogen Truck Fill This work is to relocate the nitrogen truck fill pipes from the north to the east side of the auxiliary building. All pipe has been installed except for valve installation and tie-in of the extension to the existing piping.
- 17. ECN 5519--Plant Crane Escape Devices Structural members used to attach the escape devices to the two turbine building cranes above the elevation 732 floor, as well as to the auxiliary building crane above the elevation 734 floor, have been installed. These members are also to be installed on the polar cranes in the reactor building as authorization to perform this work has now been granted.
l-L
Plsnt Maintenance Summary
--(Continued)
- 18. ECN'5449--6.9-kV Shutdown Board Degraded Voltage Circuitry Work has been completed to pull 28 cables between the-following panels:
-6.9-kV shutdown boards, 6.9-kV logic panels, main control room communication panel 1-N-21, and the auxiliary control room annunciation panel 0-L-4. Internal panel wiring for these panels is now in progress.
Termination of the 28 cables discussed above will be accomplished after
'the internal panel wiring is completed.
- 19. ECN 2775--Containment High Range Area Radiation Monitors Work was completed this month to pull cables outside containment for these mentiors. Completion of the containment cable pulling, radiation
-detector installation, final conduit inctallation, and cable terminations cannot be accomplished until an outage period.
- 20. ECN 5867--Fuel Transfer System
!~ Because of insufficient design.information, only the mechanical nodification portion will be partially worked prior to the unit 2 cycle 1 refueling outage.
- 21. L-DCM 1847--Chemical Feed Injection to Condensate Polishet; Discharge All hangers have been installed and'tubingiinstallation is continuing for tie-in of the chemical feed system to the condensate polisher discharge piping.
- 22. L-DCR 1883--Liquid Nitrogen Station
. Pouring of the liquid nitrogen station concrete pad is complete and l installation of the-station equipment, piping, and electrical service is underway.
l [
- 23. ECN 5050--Gaseous Effluent Radiation Monitoring
., The ventilation exhaust radiation monitor panel isolation valves have been installed during'this reporting period for the auxiliary and service buildings. This work remains to be performed for the units 1 and 2 shield building exhaust sytems and will complete this ECN.
'24. ECN 5684--RCP Motor Oil Spray Shields-t Work began late in this reporting period to prefabricate the shields.
This work is progressing smoothly and is expected to continue until the start of the unit 2 cycle 1 refueling outage. l l l i L
Plant Maintenance Summary (Continued)
' 25. ECN 5644--Hotwell Makeup and Dumpback Work is estimated to be complete early in June to prefabricate and partially install 6-inch piping asssemblies for the condensate storage tank "A". The section of piping in the pipe tunnel adjacent to the tank has been installed as much as possible at present. A unit outage
. period and coincident draining of the tank is necessary to complete the piping installation.
- 26. ECN 5847--Plant Fire Dampers This ECN authorizes changeout or modification of several fire dampers located throughout the plant. Fabrication of the negator
. spring assemblies is complete. Installation of the negator spring assemblies and post-modification testiag of the dampers is in progress. 27 ECN 5399--Refueling Water Storage Tank (RWST) Platforns (Units 1 and 2) Work began during this reporting period to install the platform and reposition the ladder leading to the top of the unit 1 RWST. The unit 2 work is scheduled to begin following completion of the unit I work.
- 28. ECN 5595--Moisture Separator Drain for Emergency Gas Treatment
~
Syr. tem (ECTS1 This ECN authorizes installation of drain piping with a trap for each train ot'EGTS duct. All pipe prefabrication is complete. Installation of the drain piping and trap will require placing the EGTS into a Limited Condition of Operation (LCO) and approval of the time to do this work has not yet been obtained.
- 29. L-DCR-1822--Condensate Sources To Secondary Chemical Feed system This work supplies two additional condensate sources to the secondary chemical feed system. Fabrication and installation of the 1-inch diameter piping is progressing. Final piping tie-in to the unit 2 gland seal water the demineralized water, and the secondary chemical feed systems will require system outages.
- 30. L-DCR-1492--Turbogenerator Governor Valve Permanent Scaffolds (Units 1 and 2)
Fabrication of steel scaffolds has begun. These permanent scaffolds are to be installed above all four turbogenerator governor valves for unit 2. This work is complete for unit 1.
Plant Msintenance Summary (Continued)
- 31. ECN 5735--Spray Hood and Valve Platform Removable Connections (Units 1 and 2)
This ECN authorizes installation of connections to each reactor coolant pump fire protection spray hood and to the valve platform located near the No. 4 reactor coolant pump floor plug on both unit upper containment end walls in order to allow easy removal of structural steel to' facilitate maintenance work. This work is complete on unit 1. The end wall valve platform removable connections were installed during this reporting period. The remaining unit 2 work will require a unit outage period.
- 32. ECN 5607--Plant Overhead Door Controls Work was . completed this month to modify various plant overLead daor controls as authorized by ECN 5t'07. Final functional testing of these doors is currently delsyed by other maintenance wars or the doors.
1 i a r
. _ . , . - - _ _ _ , ., - . , - - , - - - - . - ,-n,.. ~ , . - < - - . , . , ------r -
. APPENDIX A i
. Offsite Doxe Calculation Manual Changes CHANGE 2-DESCRIPTION OF CHANGE A. clarifying wording change is made in the first sentence of the second i
- paragraph of section 2.2.1. No model changes are reflected in this change; therefore, no evaluations are necessary. Actual change to page 19 is included. .
I w f
'. / .
4 0 e
*e
-- ,, .m e me - m ,,,
. APPENDIX A . Of fsite Pose Calculation Manual Changes ,
CHANGE 3 DESCRIPTION OF CHANGE The nuclide mix used for monthly calculations for liquid effluents was modified. Mn-54, Xe-133, and Cs-136 will no longer be considered in monthly calculations. .In their place Fe-55, Sr-89, and I-131 will be added. Actual changes to 0DCM page 21 are included. ANALYSIS OR EVALUATION JUSTIFYING CHANGE An evaluation of calculatea naclide-spacific doser fer 1932 releasen indicated that the thyroid is tae secotd nost critica.1 organ for the water ingestion pathwcy. To facilitate caleclation of this organ d3se, the nuclide mix had to be changed. Of the 14 nuclides menticned, the nuclide.; deleted contributed the lenne impact on th a total dose to t';.e organs considered. EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION This change will have no effect on calculated quarterly doses or on - setpoint determinations. The change will decrease the possibility of the monthly dose estimation procedure underpredicting doses calculated using the quarterly methodology.
~
APPENDIX A
- Offaite Dose Calculation Manual Changes Licantee Events and Sptcial R: ports (Continued) :.
CHANGE 4 Un1L 4 DESCRIPTION OF CHANGE A method for estimating the dose due to recreation was add,.d to the monthly calculation procedure for liquid effluents. Actual changes to ODCM pages 21 and 23.are included. ANALYSIS OR EVALUATION JUSTIFYING CHANGE _ A' comparison of renthly :.nd auarterly calculated doses for 1960-82 indicated that recratian accounted fcir a substantial part of the total . dose to the tiaxicam individual. Co40, co-53, ~Cs-134, and Cs-137 accounted 'for over !#5 percent of the calculated recreation dese. i l EVALUATIO110F ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMEliATIO!!., [ 4 This change will have no effect on calculated quarterly doses or on setpoint determinations. The change will decrease the possibility of
.the monthly dose estimation procedure underpredicting doses calculated using the quarterly methodology.
4 e + I i-4 @ f- -2'3- _x
7
, , APPENDIX A
. Offsite Dosw Calculation Manual Changea CHANGE 5 DESCRIPTION'0F CHANGE Correction of typographical error in definition of terms following old equation 2.22 (new equation 2.25). No model changes are reflected in this change; therefore, no evaluations are necessary. Actual change to ODCM page 27 is included.
CIULNGS. 6 _ DESCRIPTION OF ~ C11ANGE Correction of typographical errors in list of radiological half-lives in table 2.1. No model changes are reflected in this change; therefore, no-evaluations are necessary. A corrected ve'rsion of table 2.1 is attached. e m
= . . . w
APPENDIX A Of faite Drea Calculation bbnuel Changes SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING :. REVISION 7 h Page Revision TOC 1 Revision 5 TOC 2 Revision 7
'l through 2' Revision 6 3.through 4 Original 5 -.; -~~~ -
Revision 3 6 Revision 4 7 through 9 Revision 5 10 Original 11 through 13 Revision 5 14 - Revision 7 15 ' Revision 5 15a Revision 7 16 Revision 3 Table 1.1 (2 pages) Revisica 4 Table 1.2 (2 pages) Original Table 1.3 (8 pages) Revision 4 Table 1.4 Revision 4 Table 1.4A - Revision 5 Table 1.5 Revision 4 Tables 1.6 and 1.7 Revision 5 Table 1.8 Criginal Fig'tres 1.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Re'rision 2 19 hevision 7 20 - Revision 6 21 Revision 7 22 . Revision 5 23 through 28 Revision 7 Table 2.1 (3 pages) Revision 7 Table 2.2 Revision 5 Table 2.3 (3 pages) Revision 5 Table 2.4 a-c Revision 5 28 Revision 4 Table 3.1-1 (4 pages) Revision 4 Tables 3.1-2 and 3.1-3 Revision 4 - Table 3.2-1 (3 pages) Revision 4 Figure 3.1-1 through 3.1-6 Revision 4 Original ODCM 2/29/80* Revision 1 4/15/80** Revision 2 10/7/80** Revision 3 11/3/80, 2/10/81 4/8/81 and 6/4/81** Revision 4 11/22/82 (10/22/81, 11/28/81 and 4/29/82** Revision 5 10/21/82** Revision 6 1/20/83** Revision 7 3/23/83**
- Low Power license for Sequoyah unit 1
**RARC Meeting date
APPENDIX A Offsite Dore Criculation Manual Changes TABLt. OF CUNitNib (Cont'G)
- 2. Liquid Effluents 17 2.1 Concentration 17 RETS Requirement 2.1.1 17 2.1.2 Prerelease Analysis 17
. _ . . ~ . . , -
2.1.3 MPC - Sum of the Ratios 18 2.2' Instrument Setpoints 19
-2.2.1 Setpoint Determination 19 2.2.2 Post-Release Analysis 20 1 2.3 Dose 20 2.3.1 RETS Requirement 20 ;
2.3.2 Monthly Analysis _ 21 2.3.2.1 Vater Ingestion 21 2.3.2.2 Fish Ingastion 23 2.3.2.3 Recreation 23 2.3.2.4 Monthly Summary 25 2.3.3 Quarterly and Annual Analysis 25 2.3.3.1 Individual D6ses 25 2.3.3.2 Population Doses 28 2.4 Operability of Liquid Radwaste Equipment 28
- 3. Radiological Environmental Monitoring 29 3.1 Monitoring Program 29 l
3.2 Detection Capabilities 29
APPENDIX A-Offeite Dose Calculation Manual Changes For determining the beta . dose to air: Ds n *
- ni . DFpi (1.17)
'm .
where: [ Ds n = beta dose to air for sector n, mrad. X"1. = air concentration a of radionuclide i in sector n, pCi/m DFE'. = betaa to air dose factor for radionuclide i, mrad /yr per pCi/m t, = time period c,onsidered, yr Th[sectorhavingthehighest total dose is then used to check ccmpliance with specification 3.11.2.2. 1.2.2 Iodines and Particulates step 1 Doses will be calculated using the methodology described in this step. It an*f limita are exceeded, step 2 will be performad. equations and assumpticas for calculating doses fron releases of indines and particulates are as follows: Assumpticas
- 1. Doses are to be= calculated for the infant thyroid from milk ingestion and for the child bone and teen g.i. tract from 7 vegetable ingestion. -
.. 2. Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are considered for the vegetable pathway.
- 3. The highest annual-average D/Q based on-1972 to 1975 meteorological data for ground level releases will be used for ingestion pathway gl7 L doses.
- 4. No credit is taken for radioactive decay.
5.- Releases of 1-131 are considered for the milk pathway. , Sr-90 releases are considered for the vegetable pathway to the child bone. 7 i Co-58 releases are considered for the vegetable pathway to the teen j g.i. tract. t
- 6. The calculations extrapolate doses assuming that only 90 percent of the total dose was contributed.
I 7. The cow is assumed to graze on pasture grass for the whole year. l
*~
. Revision 7 L
, APPENDIX A Equations Offsite Dose Calculation Manual Changes For determining the thyroid' dose from milk ingestion of I-131: .,
DTH131
- 9131 - DF131 D/Q x 106 5 (0.9) 3.15 x 10' (1.18)
. whe r,e :
DTH131 = thyroid dose from I-131, mrem. Q131 = m nthly release Vf T-l'3T,- Ci. DF131 = I-131 milk ingestion 2 dose factor to infant, 7.24 x 1011 mrem /yr per pCi/m -s (Table 1.7) D/Q = relative d'eposition rate, 2.94 x 10 Sm 2, 0.9 = fraction of dose expected to be contributed by 1-131. 3.15 x 107 = s/yr. 10s = pCi/Ci Equation 1.18 then reduces to: UTH131 = 75.1 - Q131 I For. determining the bone dose from vegetable ingestion: Q g DF s D/Q - 106 > g ,19) DBC, =
-3.15x107(0.9) . -
5 where: DBC s = bone dose to child from Sr-90, mrem. Q s = m nthly release of Sr-90, Ci. DF s = Sr-90 vegetable ingestion dose factor to child, 1.36x1013 mrem /yr per pCi/m 2 -s. (As per Regulatory Guide 1.109 and NUREG/CR-1004 methodologies). D/Q = relative deposition rate, 7.32x10- m-2 , 3.15x107 = s/yr. 106 = pCi/Ci. 0.9 = fraction of total bone dose expected to be contributed by Sr-90. Equation 1.19 then reduces to DBC = 3511.5-Q s s Revision 5
, , - ~ -.c. -- -m, . , , . , . - , ,. , - - . . .. . ,.
APPENDIX A Offaite Dose Calculation Manual Changes For determining the gastrointentinal (g.i.) tract dose from vegetable
-ingestion:
DGI 9 c D/Q 106 (1.20)
'T = -(c0.9) 3.15 x 10'
~
Where: . DGIT = teen g.i. tract dose from Co-58, mrem Q c = m nthly release of Co-58, ci
, DF c
= Co-58 vegetable ingestion dose factor for the teen g.i.
tract, 3.87.x 108 mrem /yr per pCi/m -s. 2 (Regulatory Guide 1.109 and NUREG/CR-1004 methodologies.) 7 D/Q = relative deposition rate, 7.32 x 10 9 m 2
-3.15 x 10'T = s/yr 106 = pCi/Ci -
0.9 = fraction of total g.i. tract dose expected to ce contributed by Co-58 Equation 1.20 then reduces to I DGIT = 1.00 Q c 1 r l . t i
~ ~
Revision 7 e , -- ~ , - 3 -,. -- --- sp e- er- - - - --
APPENDIX A Offsita Done Calculation'Manua.1 Changes The results, from field tests conducted in September 1979, are expressed in terms of relative concentration r: r = 9.9x10 5 (F + f l
+ E 2
+ E 3
+
f4)
-Equations 2:.3 then becomes 9.9x10 5 (F + f y +f 2. +E 3 +f4) fl (Ry -1) + f .2(R2 -1) + f 3 (R3 -1) + f 4(R4 -1) i F (2.3a) 2.2 Instrument Setpoints 2.f.1 Setpoint Determination
~
The setpoint for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivaleut setpoint in counts per minute (cpm). The'physiccl and technicc1 description location and identificatien num5cr for each liquio effluent radiation detector is contained in
' plant documentation,
- The respective alarm / trip setpoints at each release point will be set such that the sum of the ratios (R 4 ) for all points, as calculeted by 7 Equation 2.2, will not exceed 1. The R 4 is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the respective R .
A l'arge increase would cause the limits specified in Section 2.15 1 to be exceeded.--The minimum ala~rm/ trip setpoint value is equal to the
- release concentration, but for ease of operation it may be desired that the setpoint(s) be set above the effluent' concentration (C ).
That-is, 3 S. J
= b.
J C. J (2.4) or s S.
- b. = J J C.
J where: S. = desired alarm / trip setpoint at release point j . J
. b = scaling factor to prevent alarms / trips due to variations in the effluent concentrations at release point j .
C. =- total concentration in the liquid effluent at release J point j specified by Equation 2.1, pCi/ml.
- Revision 7
.s
APPENDIX A Offeite Dose Calculation Manual Changes b._ During any calendar year to 1 3 mrem to the total body and to 1 10 mrem to any organ. To ensure compliance, cumulative dose calculations will be performed at least once per month according to the following methodology. 2.3.2 Monthly Analysis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose. If the projected dose exceeds the above limits. the methodology _in_Section 2.3.3 will be implemented. 3
-The 11 nuclides (listed below) contribute more than 95 percent of the dose to the total body and the two most critical organs (bone and gastro-intestinal tract (G.I. tract)) for both water and fish ingestion and shoreline recreation.
H-3 Co-58 Sr-90 Cs-134 7 P-32 Co-60 Nb-95 Cs-137 Fe-55 Sr-89 I-131 A conservative calculation of the mcnthly dose will be done according tx) the following. procedure. First, the monthly operating report containing the release data teill be obtained and the activities released of each of the above eleven radionuclides will be noted. This 3 information will then be used in the follcwing calculations. 2.3.2.1 Watar Ingestion The Jose to an individual from ingestion of water is described by the follcwing equation. . 11 ~ D.= 5 J 1
,g5 (DCF)I.J Iij, rem (2.11) i=1
.- ' Revision 7
^
APPENDIX A
, Offsite Dote Calculation-Manual Changes 2.~3.2.2 Fish Ingestion
~
The. dose to .an individual from the consumption of fish is dggeribed by Equation 2.11.
~
In this case the activity. ingested of-the i radionuclide (Igj) is described by M ij ., pCi- (2.14)
~
I 1.3 ~ = . A1Bf
.-Fd (7.34x1010) whe' re:
A..=-activity 1 released of i th radionuclide during the month, pCi B. 1 = effective fish concentration factor for tlie ith radionuclide pCi/g, ses attached as Table 2.2. pCi/mL
-M..
1J
= amount.of fish eaten monthly by maximum individual corresponding to age group selected for the critical DCF s.above-(Adult: 1750g, Child: 575g; Regulatory Guidd 1.109).
F- = . average river flow at Chickamauga Dam for month (cubic feet per second) 3 d =- fraction of river flow available for dilution (1/5's
. 7.34x1010 = conversion from cubic feet per second to milliliters per month.
- The dose. equation then becomes 11
, D '=-7.17x10
- 9
-F fA i=1 i
B 1 (M -DCF)fj, mrem (2.15) Considering-the conversion factor from rem to mrem. 2.3.2.3- Recreation The total body dose to an individual via the shoreline recreation pathway is described by the following equation. For this calculation, the total dose is estimated based on a calculation for Co-58, Co-60, Cs-134', and Cs 137. . These four nuclides are expected to contribute over 95 percent of the recreation dose. 4 D= 1 67], mrem (2.16) 0.% [(RDCF)1 - (1 8760 i=1 wi, ,~ - . .. - -" - -
APPENDIX A
.g Offeite Don Calcule. tion Manual Changen D = dose to the total body from plant releases, mrem -
1 g = 4 radionuclidesconservative correction factor. for considering only RDCF. = shoreline recreation dose commitment factor for the ith 1 radionuclide (mrem /yr per pCi/cm 2) . See attached table
2.3. (Note
For Cs-137, the dose commitment factor for its daughter,~Ba-137m, is assumed.) (1 . = concentration of i th radionuclide in shoreline sediment (pCi/cm2 ), as described by the following equation (based on equation A-5 in Regulatory Guide 1.109). *
~
.(t = 100 RHL1C1 W [1 - exp (-Ai t)] (2.17)
Where: 100 = transfer constant defined in Regulatory Guide 1.109 RHL 1
= radial.ogical half-life of the i th radioisotope, days,.
from table 2.1 - C. 1
= ccccentration of i th radionuclide in the Tennessee River, pCi/mL. C. = A./(F d 7.34x101c) 1 2 7
A. 1
= activity released of i th radionuclide during the month, pCf.
i F = tverage river flow at Chicksmatiga Dam for l thh a.onth, cubic feet pet second d = fraction of river flow available for
, dilution (1/5) 7.34x1010 = 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) At = 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 (s 10 h/ week) 0.4 (fractional exposure for yr worst quarter) + 3 (months / quarter) 8760 = conversion from year to hours.
' Revision 7
.y.
~
/TPENDIX A Offeite Dose Celculation Manual Changes The dose equation then becomes :
DL=f(0.0823Aco-60 + 0.0013 ACo-58 + 0.0218 ACs-134 (2.18) +
~0.0356 ACs-137) 2.3 2.L4 Monthly Sumnary
'If.these calculated monthly doses exceed limits specified in Section 2.3.1, then a more-accurate and complete calculation will be done as described in Section 2.3.3. 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 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.
2.3.3 Quarterly and Annual Analysis A complete analysis 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 calculatea using secticn 2.3.2 methodology and will also include an approximation of population doses. 2.3.3.1 Individual Doses , th < The dose to the the j organ of the maxioua individual from n'nuclides,
- Dj , is described by 5 m Dj= D (2.19) ijk, rem k=1 i=1 m 2 5
=
[(IDCF)(3 xlik] + [(RDCF)ijk ' b ik Tk $] (2.20: i=1 k=1 k=3 where: th
~
D ijk
=
dsetotggj organ from the i th radionuclide, via the k exposure pathway, rem. J = the organ of interest (bone, GI tract, thyroid, liver, total body, and skin.) k = cxposure pathway of interest: (1) water ingestion, (2) fish ingestion, (3) shoreline recreation, (4) above-water recreation, (5) in-water recreation. Revision 7
APPENDIX A Offsite Dove Calculation Manual Changes
= th :
(IDCF)13 ingespgon dose commitment factor for the j organ from .
,the i radionuclide, rem /pci. For the combination of pathways considered and the nuclide mix expected, the maximum exposed individual will be an adult or child.
. Table 2.1 is a list of ingestion dose factors for the
. ,two age groups.
th the activ radionuclide, l ik = via the k{gyexposure ingestedpathway, of the ipCi. 117=CV1n (2.21) For the fish pathway .
~
li2 = C B f1M . (2.22) th C. = concentration of the i radionuclide in the 1 Tennessee River, pCi/mL C i = Af/(F gd) (2.23) A. = activity released of i th radionuclide during the 1 release period, pCi. - F = total river flou at location a during period, mL. I 3 2 = locetion of interest (for dose to the maximum individual
. the first down-river exposure point is used. For the population dose, various down-river locations are used tc account for the total exposed population. Table 2.ha gives the river location of public water supplies; tables 2.4b i- and 2.4c give the boundaries of the various reaches in which concentrations are' calculated for the fish and recreation ;
pathways.) d = fraction of river flow available for dilution (1/5 above Chickamauga Dam, 1 below the dam). V = average rate of water consumption per Regulatory Guide 1.109. For maximum individual: Adult - 2000 mL/d Child - 1400 mL/d For average individual (population): Adult - 1010 mL/d Child - 710 mL/d n = number of days during the release period, day. th Bi = bioaccumulation factor for the i radionuclide in fish, pCi/g per pCi/mL, from table 2.2.
.- -J 5- 7 Revision 7
,n APPENDIX A ~ ' '
, fe Offaite Dose Calculation Manual Changes _
/
M = amount of fish consumed during the period (fraction -
~ f year times the annual consumption rate pdr11teg'ulatory o
Guide 1.109.) s . For maximum individual: .
~ '
- Adult - 21 kg/yr > 4 Child - 6.9 kg/yr For average individual (populaihion): .- .
~
6.9 kg/yr ' Adult - Child - 2.2 kg/yr . s (RDCF)ijk=recreationgsecommitmentfactorfggthej t th' organ s from the i radionuclide via the k pathway: mrem /yr per concentration ((ik) in medium; from table 2.3.
- I ik ='the concentration of the i th mental medium pertaining to the radi?Ruclide k pathway. in the environ-For above-water and in-water pathways
, lik
- b i5 =C i (2.24)
Ior the shoreline pathway, a 15-year buildup in tne - seciment of the lake is assumed (per Regulstory Guide , N 1.109 equation A-5).
.(i3 = 100 RMLi, C1 V {1-exp (-A1 -
t)] (2.25)I. where
. 100 = transfer constant as defined in Regulatory Guide 1.109.
RHL. = radiological half-life of the i th isotope, days, 1 fro.n table 2.1. 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 1
= 0.693/RHLi .
t = buildup time in sediment, assumed 15 years, per Regulatory Guide 1.109. Tk = assumpg exposure time of maximum individual for the k pathway l
- 3) shoreline 500 h/yr (s10 h/ week) l 4) above-water 1800 h/yr (6 h/d, 300 d/yr)
.5) in-water 920'h/yr (6 h/d, for five summer months) l
~
7 Reviston 7
~
,., , APPENDIX A q; !Offinte Dosa Calculation k nual Changes
~
f
& = fraction of annual exposure foe each quarter :.
./ '
-~ / ls,t Quarter , Jan. -March --1 0.1 2nd Qdrter April-June 0.3 3rn-Quarter- July-Sdpi. 0.4
,/
~
#.. 4th3juarte'r Oct.-Dec. 0.2 v,
t,. ,- .
-2.3.3.2/ Population doves
- ;f~ %
.g e., f, , - ~-1 . j
' Th'e; tqtal.' dosb fromls tl-3"T,TL*fftMtys "f6-' titMbrgan of the population , A . ,
^
s' , J
. frod'm-nsclides at n'iocations is described by v' ,
c - n 5 .m , aj -
- m a s
ijkt (2.26) 1 W '.t = 1 k=1 i=1
. a 'n 5 m
=
Dijg Pkt (2.27) 5
. ,x ,
wQ./ ' k=1 1 = 1 -. .
., , , ,.I - 1
, wh.ere a
ij k1 ' A928 E .t,he~ j tr' organ of t g total population,from the
/1, . radionuclide via the k . pathway at location 2.
, fs , , m.
/D{3gN a dos'e to fadividual as ilescribed in section 2. 3.3.1 at lo, cation f. t
.~
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nu?.ber- of peopler exposed via the k th pathway at
's e O k1. 'e l'oedtion 2, froni tsble 2.4'.~a-c .
- The population
~E ,/ is assuffd to ccisist of 71 percent adults and 29 percent children (,from1 Appendix D, Regulatory r '
Guide 13109 - the value ' for children includes x
,. teenagers') ._ -
7 , 2.4 iOperability of Liquid Radwaste Equiicent Specification 3.11.1.3 of the Radiological Effluent Technical Specifications requires that thc' liquid radwaste system sball be used to reduce the radioactiye materials in liquid _ wastes prior to their discharge when the projected d.ose due to liquid effluent releases to unrestricted areas (see Figide 2.1.1-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.21 mrem to any organ. Dosss Mll be projected monthly to assure compliance. p
.f
-37 7 Revision 7
~. . . . . - . . . .
APPENDIX A
, ; l'.
~
3 Offsite Dose Ca'1culation Menual Changes x m 1. m+ .
#4 s .
CHANGE 1
.?
3 1 . :, i DESCRIPTION OF CHANGE g*
- x. -
procedure for estimatiing ingestion dose due to atmospheric releases of Co-58 was added to the monthly dose' calculation procedures. Actual changes to'pagea 14 and 15 are included. -
t , ANALYSIS OR EVALUATION JUSTIFYING CHANGE v w . A comparison of monhhly and-quartarly calculated doses for 1982. indicated that Co-58, under certain conditions, is a significant contributor to the
, total dose,to the gastrointestinal tract.
1 e EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION
. age
-'d T .
13- , u This change will have no effect on calculated quarterly doses or
$ setpoint determinations. The chi'nge will decrease the possibility of the C
- monthly dose estimation proced6re underpredicting doses calculated using
;y. ,
-the quarterly methodology. .
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APPENDIX A Offsite Dose Calculation Manual Chanr,es
. 3.0. Radiological Environmental Monitoring 3.1 Monitoring Program An environmental radiological monitoring program shall be conducted in accordance with Technical Specification 3.12.1. The monitoring program described in Tables 3.1-1, 3.1-2, and 3.1-3, and in Figures 4 3.1-1, 3.1-2, 3.1-3, 3.1-4, 3.1-5, and 3.1-6 shall be conducted.
Results of this program shall be reported in accordance with Technical Specifications 6.9.1.6 and 6.9.1.7. The atmospheric environmental radiological monitoring program shall consist of 12 monitoring stations from which samples of air particulates, atmospheric radioiodine, rainwater, and heavy particle fallout shall be collected. The terrestrial monitoring program shall consist of the collection of milk, soil, ground water; drinking water, and food crops. In addition, direct gamma radiation levels wil] be measured in the vicinity of the plant. The reservoir samnling program shall consist of the collection of
. samples of surface water, sediment, and fish.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to-malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. 3.2 Detection Capabilities-
+
Analytical techniques shall be such that the detection capabilities listed in Table 3.2-1 are achieved.
- 9We
--- 7 Revision 7
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u 0 0 0 o 0 O 0 0- 04 0 0- 0 7D-0 0-0-0-0-0 O' -01000V0t0 - - - - - - M LCo EEEEEEEEEtEEEEEEEEECErEE0EEEEE0EEEEE0EEEEEEEEEEEE I CR 1 49061675z1O022E99000o03821 70 S1 F534S1 5S4 5E 4 a4 a654 n HCY 111229553 . n. 5.B 00
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{ tErEUCEELLEELErEEECEEEEEEEEEEEPEEECEF0: t0464356O5B9V 757E6791 44417504 S987565 V4 F 4 770. ;1 8. ;-3 3.9; 3, u. 5 8 7 5 7 91. T . 5 2. ;D 0 3 2. 9 4. T. 3. . 1. ;1 8. 3 4. 5F 2 C I C C1 ; 7 .25 s . 6 5. ;1 8 2; H. T . 7 47a5 U CG 697112854 a4-72 a1 2522231 252l12241193251 4R a314442943
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f , APPENDIX A s Offnite Do n Calculetion Manual *Ch ngm Tabic 2.1 (continued) Sheet 3 of 3 1 NUCLIOC HALF-L1rE - 00SE CCPPITNEhT FACTORS --- (REP /UCII (UAYS) avuti EHILL
, AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CCCCCCCCCCCCC CCCCCCCCCCCCCCCCCC CCCCCCCC CCCC CCCC C i
ucht ha I RACT-~TM R01 u 30 TAC BOEY ETVER "~ 00NE GI- T R ACT- T HYROID To T AC-1100Y~t-1 VCR
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- a .x,t + u a 41'0E;GI- 2'03F;02--~3T00 P OI 1.'70E.0C ~ 1 '. 4 0 E + 0 0 2.10E + 01-~ 2.33E-02 37 0 0E-01 177CE+ 0 0 1.4 0E + 0 0 -
PH-212 1.20E-01 7.57E-02 5.22E-04 2.57E.03 5.e5E-03 1.20L-01 7 .5 7 E -0 2 5.22E-04 2.57E-03 5.85E-03 Pe-214 - 4.4JL-01 1.s6E-02 J . c3ETJ47.T4E~-0 3~T71 ?E;0 F5. 6 4 E -D E - 2. 5 7E;0 5 3.0 3E- 0 4~~ 3.14 E;V3 1 Ur: C F 176~4 E-35 2CP TE-0 5-BI-212 ;4.21E-02 3.03C-04 S.90E-03 4.971-05 1.26E-04 7.24C-05 3.03L-04 5.70E-03 4.97E-05 1.2GE-04 7.24E-05 H17214 1.JBE;02 4.1CE;G5 3mt:0 3- ST 11E;36' '2.12 E-0* ~ 1;5PC-05 4.l f.E-05 3.1 PE-0 3 5711E-0 6 2 L 9 7E-0 5 1. 5 AE-0 *- PC-212 J.bOL-1z 1.50C-33 9.17E-13 3.4dE-39 1.96E-1E 1.0aE-33 1.50r-33 9.17E-13 3.4fE-34 1 96E-15 1.0PE-33 P C71, el.a9E709 4.8 0G 12~~G2 AI";10 -~'G01E;14 G 3 C C-W 3 ;35E;13 4.
- 0 E- 12 ~ 4 W2 P E410 s.01E-14 1;30E-12~~3;35E PC-216 1.74E-06 9.350-07 3.6HE-07 3.11E-09 1.85E-Oe 7.3*E-04 9. 33E- 0 7 3.6BE-07 3.11E-09 1.P5E-08 7.39E-C8 PO-21h .e;T2t-uJ 5.e,0TT05- C W4E;04-~1Tshr:06 e.62E-0( ~1T11E;35 7. 60 E20 5-~678 4 E- 0 4 a.64r-Ct. n.62E50u 4 211 C-0 5--
RA-224 ~3166E+00" 3.30C+ 00 6.60E-01 8.32E-02 7.4 7E-02 H.900-02 3.30E*C0 6.60E-01 A.32C-02 7 47E-02 P.9CE-C2 RA-226 3.utt+ou 4 . 3 0NO r~33 0 E; D i ~5. 9 DG O 1-- 3140 E
- C C'~~ 5. t CE- 01 4 ;30E + 01 3.300-C1-"3;9;E-01 3140E +00- % 90E RA-22A TVDVF 2.10E+01 7.19E-02 4.00E-01 1.70E+00 4.0CE-01 2.10E+01 7.14E-02 4.0 0E -01 1.7 CE +0 0 4.0 0 E -01 AC-224 e .55U01-~~374 EE; 0 3 4. 0 7 E;0 3-~6T1'3 E- 0 5 17 91 E;0 4 --~3 ; E 4 E;0 4---~374 P C- 0 3-~ 8. 0 7E;C 3 s.13r-05 1775 E -0 4-3.5 4 E-0 4-TH-224 6.wD u z ' 4.10t+0C 4.7CE-01 7. 4 2E- 0 3 3.nCE-02 2.34E-02
- 4.10E+00 4.7CE-01 7.42E-03 3.*0E-02 2.34E-32 TH-233 2.81E+07 1 T 0i T01 1. TO C 01'~C. 5 Etr0'3~ C2 4 E ;0 2~~2T15 C;02 1*.6CC'+ 01-~'1;8 0 E-V 1- 4T5 EE477- 9724E;0 2 2;1 rt-02 -
TH-232 u.11L+1z 1.H0E+01 1.50E-01 3.94E-C3 9.63E-02 1.*4r-32 1.80E+01 1.50E-01 3.94E-03 9.63E-02 1.RPE-02 TH-234 z .CE701~-~~~~G 1t'705-- 1;40E;01 1T4DC ~0 6~~ eG3 5E -t 4 - l . 46E-05
~ 4.~ 91 E -0 5 1.60 E-C r~~~1 ; 6 0E-06 6. 3 9E-0 4 13 4 6 E-0 5-PA-234 a . 79t ;Ur- 3.00t-04 1.11E-02 7.20E-06 3 12E-C4 ?.it:E-C4 3.UCE-04 1.11E-02 7.20E-06 3.12E-34 2.2dE-04 U-234 e.71U UT 3.T0LTd l~1!4 0C '01 CT32E;02- 2;30E.C O-~6; 32E-02 3 ;1 CE + 01 1 ;a:E-01 GT32C- 0 2-- 213CE + 00 6. 32E I L-233 1.6JL+1z 2.00F+01 1.70E-01 S.63E-02 2.0CE*0C 5.35E-02 2.80E+01 1.70E-01 5.63E-02 2.00E+00 5.35E-02
] lu P7234 NP-239 2.12C + 0 0~ ~ '4.4 2f. -0 3 3. 21 E-0 2 1.22E-05 4.03E-04 1.cet-03 '-
- 725T+UF 1.191.-06 2.40E-32 6.45E-04 f. 4SE-0F 1.17E-07 4.42E-03 3.21E-02 1.22E-05 4.03E-04 1. 0 F E - 0 3 -
3 5.2SE-06 2.F9E-02 2.65E-07 2 65E-07 3.7 7E-0 7 - FU-zw J . z 0D 0 4--- ~~~2;TrJD O F 2 ;10 E- 01 3 72 3 C- 0 3-~ 2; U 3 E-0 7~ 4 7 4 0 E - 01 2.10 C + 0 0 2.10 E-01-3 323E-0 3-2 s H 3 E-0 2-4 6 4 0 E Pt-239 c . et 0E~e U E~~ 2.60L*00 2.00E-01 3.65t-03 3.13E-02 4.50r-01 2 60E+00 2.00E-01 3.63E-03 3 13E-02 4.90E-01 WTa z.ast +06 27r.0D00 2700E;01 3;G2C-Ur 3;13Ew0e 97CC-51 e .6 0E + 0 C 210 0 E-01-376 2E -0 3-J a 15 E-0 2-4.9 0E PU-241 5 . J # UO 3-- 9.H3E-02 9.92E-04 7.45E-05 6.19C-04 9.tof-05 4.43E-02 9.92C-04 7.95E-05 6.19E-04 9.50E-03 FU-24z 1.J(L+oM z .6 0UV u t .'7 0r:0'r- 3!WW0 a e..8E202 4~.FCC;01 e;6 CD 0 07-~'70 . CSU1 a . 4 5C4 3--~2?1tsrat2-417 C E= 01 AP-241 1 55L+03 H.00C+01 2.10E-01 1.200-01 1.0CE+0C 1.70E*01 8.00E+01 2.10E-01 1.20E-01 1 00E+00 1.70E+01 7-2 4 z 6 . t ML O'1 V!!iG 0 J v.26E;0 T~170GE;05 1.4 4E-C4~1;51E-C3 ~ 5 19E-03 % 2EE-0 3-1.-V6E+ 05-1.4 4 E-0 4-1.51E-0 3-Ar-243 2.65E+06 '.50F+01 2.20E-01 1.30E-01 1.00E+00 1.70E*01 e.5CE+01 2.20E-01 1. 3 0E - 01 1 00E+00 1.7CE+01 Ch-242 1. ha t. + 0 g 1.u?E+ 0 0 273GE;01 z .72E;0 3 2;5 PE-0 2~4 '.49E -01 1.5 c E+ 0 0 ~2. 3 0 E4 01-~2772E + 0 3-2 5 *nE 4 2 4 c E _ CM-243 1.04E+04 4.30E+01 2.50C-01 G.22F-02 7.10E-01 1.20r+01 6.0CE+03 1.000+03 1.01E
- 0 3 2.01E+03 1.0CE+03 CM-244 6.61T+03 _
J.90C7DI 2.20L-ul 6.f0L-we 57EUE;01 9. J CD 00 J;40E+31 e.20E-ul b . 4 0 E* D7 5 .Gtt*31---9 73 0E
- 0 0---
m E r un p
- Dose factors were taken from the following references in order of preference:
- s t W l. Regulatory Guide 1.109, USNRC, October 1977 "
- 2. NUREC/CR-0150, D. E. Dunning, ORNL, October 1981
- 3. ORNL-4992, C. C. Killough and L. R. McKay, March 1976
! ~T TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Daisy, Tennessee 37319 'JUN 151983 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the May 1983 Monthly Operating Report for Sequoyah Nuclear Plant. Very truly yours, TENNESSEE VALLEY AUTHORITY [ C. C. Mason Power Plant Superintendent Enclosure cc (Enclosure) Director, Region II Director, Office of Management Director, Office of Management Information and Program Control Nuclear Regulatory Commission Nuclear Regulatory Commission 101 Marietta Street Washington, DC 20555 (2 copies) Suite 3100 Atlanta, GA 30303 (1 copy) INP0 Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, GA 30339 (1 copy) Nuclear Regulatory Commission Washington, DC 20555 (10 copies) Mr. A. Rubio, Director Mr. Bill Lavallee, NSAC Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 (1 copy) Mr. R. C. Goodspeed
.MNC 461 Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA 15230 (1 copy)
An Equal Opportunity Employer I
-.}}