ML17341A868
| ML17341A868 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/30/1981 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17341A867 | List: |
| References | |
| NUDOCS 8202080321 | |
| Download: ML17341A868 (42) | |
Text
STEAM GENERATOR REPAIR PROGRAM FOR TURKEY POINT UNIT 3 RADIOLOGICALPROGRESS REPORT - NO. 3 FOR THE PERIOD NOVEMBER 0, 1981 THROUGH DECEMBER 30, 1981 DOCKET NO. 50-250 LICENSE NO. DPR-31 FLORIDA POWER AND LIGHTCOMPANY 8202080321 82020i PDR ADOCK 05000250 P..
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TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
2.0 OCCUPATIONALRADIATIONEXPOSURE 2.1 General 2.2 Description and Format of Exposure Data 2.3 Discussion of Exposure Results 3.0 APPLICATION OF DOSE REDUCTION TECHNIQUES (ALARAPRINCIPLES) 3 3.1 General 3
3.2 Transfer of Steam Generator (S/G) Lower Assemblies to S/G Storage Compound 3;3 Contamination Control Envelopes and Ventilation 3.0 Installation of Steam Generator Lower Assemblies (SGLA's) 3.5 General Techniques and Practices 5
0.0 RADIOACTIVEEFFLUENTS AND SOLID WASTE O.l General 0.2 Liquid Releases 0.3 Airborne Releases 0.0 Solid Radioactive Waste
5.0 CONCLUSION
S AND OBSERVATIONS TABLES TABLE 1 TABLE 2 TABLE 3A TABLE 3B TABLE 3C TABLE 0 TABLE 5 TABLE 6 Description of Major Tasks Personnel Exposure Summary - Per Task Summary of Preparatory ActivityExposures Summary of Removal ActivityExposures Summary of Installation ActivityExposures Personnel Exposure Summary - Per Phase Summary of Radioactive Effluent Releases Summary of Solid Low Level Radioactive Waste Shipments 8
10 12 10 16 18 19 22
1.0 INTRODUCTION
Radiological Progress Report No. 3 contains information pertaining to the radiological aspects of the Unit 3 Steam Generator Repair Program (SGRP) for the period November 0 through December 30. This information-includes the following:
a.
An assessment and summary of the occupational exposure and labor expended for each reporting period (throughout the project).
b.
An evaluation of the effectiveness of dose reduction techniques (ALARA principles).
c.
An estimate of the radioactivity released in liquid and airborne effluents.
d.
An estimate of the solid radioactive waste generated including volume and radioactive content.
, Significant project tasks performed during this reporting period included:
1.
Completion of steam generator (S/G) storage compound.
2.
Draining of S/G lower assemblies and placement of S/G lower assemblies in S/G storage compound.
3.
IVelding and closure of S/G lower assembly vent and drain fittings.
0.
Removal of S/G transfer bridge.
5.
Installation of S/G upper assemblies (includes upper girth weld, placement of secondary side internals, and stress relieving operations).
6.
7.
Installation of S/G lower assemblies (includes such operations as lower girth weld, channel head welding, and stress relieving).
Installation of main steam and feedwater piping.
8.
Installation of concrete stop-logs, concrete forms, rebar and preparation for placement of new concrete.
9.
Preparation of S/G divider plates for welding.
10.
Preparation and installation of miscellaneous piping in S/G cubicles.
Several on-going activities also performed during this period included:
maintenance of temporary scaffolding, cleanup and decontamination, maintenance of temporary electrical power and lighting services, installation of temporary shielding, health physics support and project supervision.
2.0 OCCUPATIONALRADIATIONEXPOSURE
'.1 General As indicated in previous progress reports, occupational exposure to radiation may be considered the major radiological impact of the SGRP.
The program developed to collect exposure information and provide accurate assessments of tasks performed is discussed in detail in Section 2.1 2.3 of Radiological Progress Report No. I. This program was utilized throughout this reporting
.period.
A description of the thirteen (13) major tasks is indicated in Table 1.
2.2 Descri tion and Format of'Ex osure Data Table 2 presents a summary of the occupational radiation exposure expended in person-rem and the labor expended in the radiation field in person-hours through this reporting period (i.e., from project commencement on 20 3une 1981 to 30 December 1981).+
Also included are the original estimated expenditures.
The following comments are provided for clarification and should be considered when reviewing the data presented in Table 2.
a.
Several activities performed during the repair effort which were not described in Table 1 have been appropriately placed into one of the major task categories in Table 2 and accordingly accounted for.
b.
Exposures received by certain pre-identified personnel (e.g., health physics, QC/QA, etc.) performing functions not directly attributable to any one task are listed separately in Item 7.
c.
Information detailing exposures reported for specific activities within a major task is contained in the data base.
This information is utilized to "track" exposure for the time period of interest.
A detailed summary of the personnel exposure expended through this reporting period for preparatory, removal and installation activities are presented in Tables 3A, 3B and 3C respectively.
This summary includes both the labor and exposure expenditures and the original estimated expenditures.
These tables list a more detailed breakdown of specific job activities which have been incorporated into the appropriate major task descriptions listed in table 2. Table 0 presents a general summary of both labor and personnel exposure expended for each phase of the repair project with the original estimated expenditures.
The following comments are provided for clarification and should be considered when reviewing the data presented in Tables 3A, 3B, 3C and 0.
<<Self-reading pocket dosimeter (SRPD) results are used to report person-rem since exposure information is immediately available upon exit from the RCA and accordingly recorded in the computer data base.
Since thermoluminescent dosimeters (TLD's) are processed primarily on a monthly basis this information could not be readily incorporated into the exposure expended for each specific activity.
Historically, SRPD results are higher than TLD results primarily due to drift (caused by factors such as heat and humidity, and initial charging).
Therefore, the accumulated dose reported may be considered as conservative.
a.
Activitystatus indications are given to allow comparison of actual versus estimated person-rem expenditures.
b.
Activities indicated as in progress may require additional exposure prior to completion of the activity; therefore a valid comparison at this time is not justified.
Co For completed activities it should be noted that small amounts of additional exposure and labor may appear sometime after completion is indicated, as a result of such factors as: field changes to procedures, work involving activity related to support equipment, localized work area cleanup, etc.
2.3 Discussion of Ex osure Results A review of the data presented in Table 2 shows that the total occupational radiation exposure recorded for all major tasks is approximately 70% of the original total estimate.
These exposures are recorded by computer acquisition as discussed in Progress Report No. 1. Table 2 includes all exposure expended through December 30, 1981 and willcontinue to be used for accumulation of all personnel exposures through project completion. The exposure expended to date is primarily attributed to repair project removal and installation activities as indicated in Tables 3B and 3C.
Tables 3A and 3B show that the total occupational exposure accumulated for completed activities to date is approximately 208 and 552 person-rem respectively as compared to their respective original exposure estimates of 283 and 1,016 person-rem respectively.
This indicates that the total actual exposure expended for the completed activities shown in Tables 3A and 3B was approximately 00% less than the total estimated exposures for those activities.
Table 3C shows that the total occupational exposure accumulated for installation activities in progress to date is approximately 612 person-rem as compared to the original exposure estimate of 600 person-rem.
The exposure to date attributed to S/G lower assembly installation (appro'ximately 000 person-rem) is significantly higher than the estimate of 200 person-rem (items 2 and 3 of Table 3C).
The information for all phase activities in progress or completed (as detailed in Tables 3A, 3B and 3C) is summarized in Table 0. The total exposure expended during this reporting period was approximately 550 person-rem.
The exposure expended for miscellaneous phase activities (approximately 37 person-rem) is also included in this reporting period as shown in Table 0. Detailed exposure information for this phase will be presented in the next progress report.
3.0 APPLICATION OF DOSE REDUCTION TECHNI UES (ALARAPRINCIPLES) 3.1 General This section discusses the techniques and practices which have been effective in providing dose reductions to personnel during the reporting period.
Where available data permits, the following evaluations include a quantitative assessment of the person-rem savings which can be attributed to the techniques Usedo
. 3.2 Transfer of Steam Generator Lower Assemblies to S/G Stora e Com ound As indicated in Radiological Report No. 2, the Unit 3 Steam Generator Lower Assemblies (SGLA's) were placed in temporary storage until the S/G storage compound was completed.
To reduce dose rates in the temporary storage area, the SGLA's were filled with demineralized (Dl) water. Vent and drain fittings were installed for this purpose.
The resulting reduction in general area dose rates indicated that an exposure savings was realized.
This savings cannot be easily quantified since the majority of personnel benefiting from the reduced dose rates were those proceeding to and from work areas.
Prior to placing the SGLA's in the completed storage compound, each SGLA was sampled for radioactivity and drained.
Sample results indicated no significant activity; however, the water that was drained from the SGLA's and discharged was considered a controlled release.
The small amount released was approximately.017 mCi with Co-60 the predominant isotope.
This amount is included in Table 5.
The exposure expended as a result of transferring the'SGLA's from the temporary storage area to the S/G storage compound and welding the SGLA temporary filland drain fittings was approximately 13 person-rem.
Surveys taken outside the S/G storage compound after placement of the SGLA's indicated approximately 0.1 to 0.0 mR/hr contact with the walls and approximately 15 to 20.mR/hr contact with the roof of the storage compound.
The compound is located in the Radiation Controlled Area (RCA).
3.3 Contamination Control Envelo es and Ventilation The use of contamination control envelopes and filtered ventilation system proved effective during S/G lower assembly installation.
Welding and backgouging operations resulted in low-level airborne radioactivity levels in the channel heads and enclosures.
Airborne concentrations in the 10-8 >Ci/cc range were detected and confined to the enclosures with no significant airborne activity detected outside the S/G channel head enclosures.
Use of the S/G filtered ventilation system (as described in previous reports) effectively maintained a negative pressure in the work area thereby preventing the release of airborne radioactivity outside the S/G channel head enclosures.
It is planned to utilize contamination control envelopes and filtered ventilation throughout S/G lower assembly installation activities.
3A Installation of Steam Generator Lower Assemblies (SGLA's)
Exposure reduction techniques utilized for S/G channel head remnant weld preparation as discussed in Radiological Progress Report No. 2 were also used for SGLA installation.
These techniques included:
a)
Controlling access/egress to S/G work platforms from outside the biological shield wall where dose rates are typically ten times Jess than dose rates inside the shield wall.
b)
Installing contamination enclosures at the S/G manways to minimize airborne radioactivity and the spread of contamination to adjacent areas.
c)
Limitingaccess/egress to the S/G channel head through the S/G cold leg manway thereby allowing a filtered ventilation system to exhaust air from the S/G channel head hot leg manway.
d)
Utilizing ventilation duct work providing cool air as much as practical to provide some relief to workers in the channel head.')
Utilizingspecial channel head shielding for channel head welding and interior repair work whenever practical to reduce exposure rates.
The above techniques will continue to be utilized as necessary throughout the completion of SGLA installation.
To date the exposure expended as a result of SGLA installation is approximately 000 person-rem.
without the benefit of S/G channel head shielding, the exposure would be approximately 0000 person-rem.
Thus, a conservative savings of approximately 0000 person-rem was realized.
The exposure savings for all SGLA installation activities as a result of S/G channel head shielding will be discussed in a future report.
3.5 General Techni ues and Practices In addition to the assessment of dose reduction techniques described above, it is important to note some of the more general techniques and practices employed to maintain adequate control of personnel radiation exposure.
These practices include the following:
a)
A comprehensive health physics program which includes an extensive training and radiological surveillance program.
b)
Use of repair project process sheets.
c)
Utilization of "in-containment" low-level radiation waiting areas.
d)
Use of portable area radiation monitors to provide workers on the spot continuous exposure rate information.
e)
Ongoing decontamination and periodic work clean-up program.
f)
Use of continuous air samplers in addition to periodic grab samples.
g)
Use of in-containment tool cribs and weld rod rooms.
A detailed description of these techniques and practices are discussed in Progress Report No. i.
h)
Use of a cooler system in the Reactor Containment. Building (RCB) to improve worker comfort. Although this system was not designed to cool the entire RCB, it should significantly improve worker comfort especially on the 58'levation where a large majority of the work is scheduled.
I I
i)
A communications system used by health physics and located in the vicinity of each S/G enclosure to allow direct communication with the Health Physics Shift Supervisor.
This system enables the health physics technician to maintain continuous communication with the shift supervisor thereby minimizing delays (and person-rem expended) on the job.
j)
Multi-badging for evaluation of personnel exposure for those tasks performed in relatively complex radiation fields.
k)
Use of temporary lead shielding in high occupancy/traffic areas.
Experience has shown that the practices and techniques discussed in this section have contributed significantly to an effective overall dose reduction (ALARA) program for the repair project.
Updates will be discussed in future reports.
0.0 RADIOACTIVEEFFLUENTS AND SOLID WASTE 0.1 General Radioactive effluents, compromised of liquid and airborne releases, and low-Jevel solid radioactive waste produced during this reporting period and throughout the repair project to date are summarized in Tables 5 and 6 respectively.
During this reporting period Unit 0 was shutdown for normal refueling and maintenance.
The increase in activity released for this reporting period can be attributed to the fact that both Units 3 and 0 share effluent collection facilities. Thus, some of the effluent activity released as a result of the Unit 0 shutdown are included with the effluent activity totals in Table 5.
Laundry op'erations continue to be the major source of liquid releases for the Unit 3 repair project. As shown in Table 5 the composition of radioactive isotopes detected remain relatively unchanged from those detected during the previous period.
Approximately 7396 of the total activity released to date was in the form of relatively long-Jived corrosion products.
The remaining 27% was in the form of fission products (which include Cs-130 and Cs-137) and activation products.
The total activity released to date is approximately 1196 of the total estimated activity to be released during the repair project on Unit 3.
0.3 Airborne Releases Airborne releases for this reporting period originated primarily from continuous ventilation of the containment during repair activities. A summary of airborne releases is shown in Table 5 as well. As indicated in previous progress reports the particulates detected were typical of radionuclides expected as a result of an extended shutdown.
The. total activity released through this reporting period is Jess than 26% of the total estimated activity projected to be released.
0.0 Solid Radioactive Waste A summary of solid low-level radioactive waste generated and shipped to date as a result of Unit 3 steam generator repair activities is-provided in Table 6. The low-level waste shipments during this reporting period were made to both the Barnwell, South Carolina and Richland, Washington Low-Level Waste Disposal Facilities.
The total volume of solid low-level radioactive waste generated due to repair project activities through this reporting period (excluding the steam generator lower assemblies) is approximately 86% of the volume estimated in the Gould Affidavitdated 3une 12, 1981. It should be noted that the final volume of waste shipped may be less than the accumulated volume of waste generated.
This can be primarily attributed to additional volume reduction techniques used prior to shipment, which are not accounted for when initiallygenerated.
5.0 CONCLUSION
S AND OBSERVATIONS The following general conclusions and observations are based upon information contained in this report:
a)
For installation phase activities completed to date, the actual exposure expended is approximately 612 person-rem as compared to the original estimate of 600 person-rem.
Approximately 72% (000 person-rem) of the actual exposure expended for installation activities is attributed to steam generator channel head interior weld repairs and lower assembly installation activities as compared to the original estimate of 200 person-rem for S/G channel head repair and lower assembly installation.
This higher expended exposure is attributed to personnel working in radiation fields higher than originally estimated and performing weld repairs that also required more time in the higher radiation fields. With the majority of the higher exposure installation activity work near ing completion, the actual exposure expended for the entire project is expected to be lower than 2000 person-rem.
b.
Radioactive liquid effluents continue to remain within the total release estimate presented in Table 5.2-7 of the repair report.
The calculated activity is less than 11% of the estimated total activity in the Steam Generator Repair Report (SGRR).
c.
Airborne releases of radioactivity remain below the estimate indicated in the SGRR.
No radioiodine or gaseous activity was detected.
Airborne activity discharged throughout the Unit 3 repair project is not expected to exceed the estimate indicated in the SGRR.
d.
Solid low-level radioactive waste generated to date (excluding the steam generator lower assemblies) represents approximately 86% of the estimate provided in the Gould Affidavitdated 3une 12, 1981.
Progress Report Number 0 willcontain information from December 31, 1981 through March 3, 1981.
TABLE 1 DESCRIPTION OF MA3OR TASKS TASK TASK DESCRIPTION 1.
Concrete and structural steel removal and placement.
This task includes all work associated with removal/replacement of concrete and structural steel.
Removal items include: Erection of scaffolding to remove piping and electrical components, cut/removal of the concrete shield wall above EL 58'nd the floor slab at EL 58',
the concrete shield wall 'below EL 58', and removal of structural steel.
Replacement items include: Installation of rebar and cadweld splices, erection of form work and shoring, concrete placement, and installation of structural steel.
2.
Construction of pedestal cranes, preparation of polar. crane, miscellaneous cribbing platforms, S/G transfer bridge.
3.
Removal, modification and reinstallation of S/G upper assemblies and.
major piping.
20 3.
This task includes, installation/removal of the pedestal crane foundations, assembly and erection of cranes and the polar crane trolley, and disassembly and removal of cranes and the. polar crane trolley.
Items included in. this task are:
Erection/
removal of scaffolding from El 58'o El 93', removal/installation of insulation and piping, upper assembly girth cut, cutting internal pipe and structural members inside the S/G, upper assembly modifications, and the upper assembly girth weld; 0.
Construction of temporary facilities and support services.
5.
General decontamination and disposal of contaminated materials/cleanup.
5.
The major exposure items in this task are:
Routing of welding leads, installation of temporary, power for small tools and lighting,in,the area near the S/G (most will be inside the secondary shield wall between El 10'nd El 30'6"), and maintenance of temporary power and lighting for the entire outage.
This task includes general area decontamination of the containment prior to commencement of major work, continuous containment decontamination for the entire outage, and removal and disposal of contaminated material for the entire outage.
Qi
. TABLE 1 (continued)
DESCRIPTION OF MA3OR TASKS TASK 6.
Removal and reinstallation of miscellaneous piping, equipment and insulation.
6.
TASK DESCRIPTION This task includes removal of insulation from the steam generator and main steam and feedwater piping, installation of insulation on the new steam generators, and removal/installation of miscellaneous items.
7.
Non-manuals (e.g., QC, Engineers, HPs).
8.
Decontamination. of the channel head.
9.
Cut channel head and remove old S/G lower assembly.
10.
Weld shield cover on lower assembly;
- a. At channel head
- b. At transition end 7.
8.
9.
10.
The non-manual category includes health physics, quality control, and engineering personnel, visitors, and Bechtel personnel required for the entire outage.
Included in this task are mechanical grit blast decontamination of the channel head, and installation of inflatable plugs in the reactor coolant piping.
This task includes. installation of tenting and temporary shielding, cutting the transition cone, and channel head, and rigging and removal of the lower assembly to the containment equipment hatch.
The only item in this task is welding of steel plates at each end of the steam generator to provide shielding and to prevent leakage.
11.
Cut and remove old divider plate, weld new divider plate.
The divider plate was detached from the tubesheet as part of Task 9. Removal and placement of the divider plate to the channel head is included in this task.
12.
Install new S/G, weld channel head.
13.
Placement of steam generator in storage.
12.
13.
This task includes erection/removal of scaffolding, rigging and moving the new steam generator, installation/removal of hydroplugs, channel head welding and grinding, and removal of the inflatable plugs in the reactor coolant pipes.
This task includes transporting of the S/G from the containment equipment hatch into the storage compound and construction of a roof once the S/G's are in the compound.
10 TABLE 2 PERSONNEL EXPOSURE
SUMMARY
PER TASK REPORTING PERIOD 20 3UNE 1981 TO 30 DECEMBER 1981 TURKEY POINT - UNIT 3 TASK DESCRIPTION LABOR EXPENDED IN RADIATIONFIELD PERSONNEL EXPOSUREa (PERSON HOURS)
(PERSON-REM)
ESTIMATED ACTUAL ESTIMATED ACTUAL 1.
Concrete and structural steel removal and replacement.
13,660 7,605 88 56.05 2.
Construction of pedestal cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.
3.
Removal, modification.and reinstallation of steam generator upper assemblies and major piping.
0.
Construction of temporary facilities and support services 5.
General decontamination and disposal of contaminated materials/cleanup.
6.
Removal and reinstallation of miscellaneous piping equipment and insulation.
7.
Non-manuals (e.g. QC, Engineers, Health Physics).
8.
Decontamination of the channel head.
9.
Cut channel head and remove old steam generator lower assembly.
10.
'>Veld shield cover on lower assembly:
- a. at channel head
- b. at transition end
'10,280 20,600 19,120 02,310 8,850.
68,500 1,800 3,200 760 530 9,997 50,750 10,865 10,077 13,002 31,672 6,503 7,991'26'78 32 31.56 256 219.05 215 32.12 201 96.87 125 99.31
'36 100.08 210 155.12 166 97.60 00 10.10 53 16.09
11 TABLE 2 (continued)
PERSONNEL EXPOSURE
SUMMARY
- PER TASK REPORTING PERIOD 20 3UNE 1981 TO 30 DECEMBER 1981 TURKEY POINT - UNIT 3 TASK DESCRIPTION LABOR EXPENDED IN RADIATIONFIELD PERSONNEL EXPOSUREa (PERSON HOURS)
(PERSON-REM)
ESTIMATED A'CTUAL ESTIMATED ACTUAL 11.
Cut and remove old divider plate, weld new divider plate.
12.
Install new steam generator weld channel head.
13 Placement of steam generator in storage.
TOTAL Estimated Range 2,600 11,000 225 207,595+
613 38,803 331 190,277 29 23.30 200 039.69 25 30.18 2,080 1,008.76 1730-2080 Actual exposures are estimated by self-reading pocket dosimeter. totals.
This estimated total was incorrectly reported in previous progress reports as 182,800.
The correct total for the estimated task labor values should have been 207,595.
T~ABLE A
SlMARY OF PREPARATORY ACTIVITYEkVOSURES REPORTING PERIOD 4 NOVHKER 1
1 TO 0 DECBSER 1
81 TURKEY POINT - UNIT ACTIVITYDESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ES1'IMATED
~
FOR REPORTING EXPENDED STATUS LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)
PERSON BOURS PERSON HOURS)
PERSON-REM (PERSON-REM)
PERSON-REM)
(I-IN PROGRESS
- l. Initial Containment Decontamination 6,020 2.
reactor Cavity Decontamination and Inspection 2, 108 45.00 0.00 0.00 27.07 5.58 3.
Install Steam Generator Transfer Bridge 4.
Remove Emergency Containment Coolers, Control Rod Drive Mechanism Coolers and Fans, Manipulator Crane, and Rerate Polar Crane and Load Test 5.
Install Cherry Pickers 6:
Remove Reactor Coolant Pump Motors 7.
Disconnect/
Remove Permanent Electr'ical Equipment and Cables 8.
Install Temporary Power, Lighting and Electrical Cables 9.
Remove Miscellaneous Steel 10.
Install Tempo>.ary Containments and/or Ventilation Systems 960 6,860 2,430 0
430 1,148 580 1,473 5E157 2,990 386 281 2,962 1,702 1,740
'.21 11.83 7.15 0
3.31 49.48 1.25 4.29 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 7.80 7.80 17.88 2.43 2.50 11.68 7.05 12.62
0
SCARY OF PREPARATORY ACTIVITYEXPOSURES REPORTING PERIOD NOVEMBER 19 1.
TO 0 DECBSER 1
81 TURKEY POINT UNIT ACTIVITYDESCRIPTION ESTIMATED LABOR (PERSON-HOURS ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLEIE)
PERSON>>HOURS PERSON-REM PERSON-REM)
PERSON-RR I-IN PROGRESS 11.
Install Temporary, Shielding l
12.
Install Scaffolding All Levels 13.
Cut and Remove Concrete 14.
Miscellaneous Activities 1,440 5,334 9,425 1,388 1,895 3e913 5,419 2.58 13.27 58.00 85.63 0.00 0.00 0.00 0.00 31.05 9.95 45.49 59.04 TOTAL - PHASE I 34g992 31,787 283.00 0.00 247.g4
T~ABLE B
SUMMARY
OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD NOVEÃ3ER 19 1 TO 0 DECEMBER 1
81 TURKEY POINT - UNIT ACTIVITY DESCRIPTION ACTUAL ESTIMATED LABOR EXPENDED LABOR TO DATE PERSON-HOURS FERSOil-HOURS ACTUAI EXPOSURE ACIUAI EXPOSURE ACTIVITY ESTIMATED FOR REPORTING EXPENDED STATUS EXPOSURE PERIOD TO-DATE (C-CQPLETE)
PERSON-HEM PERSON-REM PERSON-REM I-IN PROGRESS 1.
Remove insulation from A, B A C steam generator IA 2.
Remove Fcedwater Piping A, B 5 C steam generator 31850 147 2,473 1A50 O.M 9.95 7,669 77BOO 0.00 70,80 C
3.
Cut A, B h C S/G Upper Assembly (U.A.) and rex've and modify U.A. internals 6,318 13,379 126.40 OAM 60.02 4.
Install tube bundle shield covers A, B h C S/G 5.
Cut divider plate 4 channel head A, B 4 C S/G - Rig to 58'levation 530 11722 978 51087 53.00
- 97. 14 0.00 0.00 16.49 72.07 6.
Rig/lift A, B 0 C S/G Lower Assembly 84 (L.A.) to cut/remove seismic ring 7;
Install tube sheet shield cover A, B 5 C S/G
- 8. Lift A, B 5 C S/G U.AA1 invert and 525 place in rack 142 2,143 6.60 40.00 6.75 0.00 O.M 0.00 0.72
- 10. 10 11.79 9.
Remove main steam piping A, B 5 C S/G 126 499 0.61 0.00 2.84 10.
Install laydown cribbing for A, B 4 C 252 S/G 58'levation 2.65
'.O.M 0,49
SUMARY OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD NOVHKER 1
1 TO 0 DECEMBER 1
81 TURKEY POINT - UNIT ACTIVITYDESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS LABOR TO DATE EXPOSURE PERIOD 'O-DATE (C-CCMPLEIE)
PERSON-HOURS PERSOiV-HOURS PERSON-REM PERSON-RBI PERSON-REM)
I-IN PROGRESS 11.
Conduct channel head decontamination
.A, BKCS/G 12.
Remove miscellaneous piping from A, B A C S/G cubicles 13.
Remove A. B A C S/G L.A. from RCB and transfer to storage compound 14.
Maintain temporary power lighting and electrical cables 15.
Maintain/erect/remove scaffolding 16.
Ongoing decon activities/remove and dispose contaminated materials 17.
Miscellaneous Activities PHASE ACTIVITYTOIALS 1,840 1,410 2,100 840 14,500 33,800 69,129 6,503 6,050 1,578 5,686 2,914 5,103 61,252 214.00 17.62 25.00 55.00 8.40 62.40 221.93 1016.00 0.00 0.00 12.47 O.M 0.00 0.00 0.00 12.47 155.12 29.79 30.18 4.70 29.85 16.57 31.M 552.48 C
~
~TEIILE C
SUMARY OF INSTALLATIONACTIVITY EXPOSURES REPORTING PERIOD
'OVEYBER 19 1 TO 0 DECEMBER 1981 TURKEY POINT - UNIT ACTIVITYDESCRIPTION 1.
Installation of A, B & C S/G Upper Assemblies
\\
2.
Weld Preparation of A, B & C S/G Channel Head Remnants 840 4,552 7.71 4.25 69.09 ACIUAL ACTlJAL EXPOSURE ACDJAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIlSLTED FOR REPORTING EXPENDED STATUS LABOR TO DATE EXPOSURE PERIOD
.TO-DATE (C-CGMPLETE)
PERSON-HOURS PERSON-HOURS PERSOiV-REM PERSON-REM (PERSON-Rf (I-IN PROGRESS 17,540 6,534 73 70 9.69 9.69 C
3.
Installation and Welding of A, B & C S/G Lower Assemblies 4.
Installation of A, B & C S/G Main Steam Piping 5.
Installation of A, B & C S/G Feedwater Piping 6.
Welding of A, B & C S/G Divider Plates 7.
Install Insulation A, B & C Steam Generators 8.
Maintain Temporary Power, Lighting and Electrical Cables 9.
Mal'ntain/Erect/Remove Scaf folding 10.
Ongoing Decon r:tivities/
Remove/Dispose Contaminated Materials 8,360 1,250 1,680 1,554 3,486 2,850 2,840 14,500 33,934 495 1,954 12 6,301 9E794 5,113 182.00 5.50 6.80 15.10 29.40 65.00 21.80 62.40 362.20 0.69 7.03 1.29 0.00 12.59 21.86 25.26 370.61 0.69 7.03 1.29 0.00 13.99 31.81 41.01
SUMRNY OF INSTALLATIONACTIVITYEXPOSURES REPORTIhG PERIOD NOVDKER 19 1 TO 0 DECBSER 1 81 ACTIVITYDESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING
~
EXPBlDED STATUS LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)
PERSON-HOURS PERSON-HOURS)
PERSON-REM)
(PERSON-REM)
PERSON-RED I-IN PROGRESS 11.
Miscellaneous Activities 27,190 22,699 174.59 55.81 66.36 PHASE ACTIVITYTOI'ALS 82,000
- 91) 397 644.00 500.67 611.57 Total Phase III (Completed Tasks OQy) 18,290 10,086 81.41 13.94 78.78
TABLE 4 PERSONNEL EXPOSURE SMARY PER PHASE REPORTING PERIOD NOVEMBER 19 1 TO 0 DECEMBER 1981 TURKEY POINT - UNIT PHASE ESTIMATED LABOR ACTUAL LABOR DESCRIPTION EXPENDED TO-DATE EXPENDED TO-DATE (PERSON-HOURS)
PERSON-HOURS TOTAL ESTIMATED EXPOSURE PERSON-REM ESTIMATED EXPOSURE EXPENDED TO-DATE PERSON-REM)
ACTUAL EXPOSURE PHASE STATUS FOR REPORTING
~
ACTUAL EXPOSURE (C-COMPLETE)
PERIOD EXPENDED TO-DATE (I-IN PROGRESS)
PERSON-REM (PERSON-REM)
(NS-NOT STARTED Preparation Removal'nstallation Miscellaneousa Pro)cot totals (Completed Phases 34p992 69,129 82,000 7~433 193~554 Only) 104,121 31,787 61,252 91g397 9,841 194 p277 93s039 283 1,016 644 141 2,084 1,299 283 1,016 644 38 1,981 1>299 0.00 12.47 500.67 36.77 549.91 N/A 247.94 552.48
'11.57 36.77 1448.76 800.42 NA NA aMiscellaneous - includes cleanup, storage and miscellaneous preparations prior to start-up.
bNA not applicable at this time.
~
~
1981 I.
LIQUID EFFLUENT RELEASES TABLE 5
SUMMARY
OF RADIOACTIVEEFFLUENT RELEASES REPORTING PERIOD 4 NOVEMBER 1981 TO 30 DECEMBER 1981 TURKEY POINT - UNIT 3 RADIOACTIVITYRELEASED IN LIQUIDEFFLUENTS (CURIES)
NOVEMBER DECEMBER ISOTOPE 11/5-12/2 12/3-12/30 TOTAL ACTIVITY TOTAL RELEASED THIS, RELEASED DURING REPORTING S/G REPAIR PERIOD TO DATE Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 Mn-54 Zn-65 1-131 Nb-95 Sb-124 Sb-125 Ag-IIOm Zr-95 7.60E-06 6.01E-03 2.58E-03 4.26E-04 6.80E-04 5.12E-05 3.32E-04 2.83E-04 6.13E-05 6.98E-05 2.02E-04 1.17E-02 3.15E-03 7.33E-05 1.95E-04 3.37E-04 1.97E-04 1.36E-03 3.55E-'03 5.68E-04 2.63E-04 7.60E-06 1,77E-02 5.73E-03 4.99E-04 8.75E-04 3.88E-04 5,29E-04 2.83E-04 1.42E-03 3.55E-03 6.38E-04 4.65E-04 7.60E-06 2.14E-02 1.08E-02 1.84E-03 3.26E-03 4.33E-04 7.56E-04 3.50E-04 1.54E-03 3.56E-03 6.38E-04 4.65E-04 TOTAL 1.07E-02 2.14E-02 3.2 IE-02 4.50E-02 Liquid Effluent Volume Released (Liters) 1.20E+06 1.34E+06 "Not detectable C
VOLUMERELEASED VOLUMERELEASED THIS REPORTING DURING S/G REPAIR PERIOD TO DATE 2.54E+06 7.13E+06
1981 I.
AIRBORNE RELEASES A.
NOBLE GASES ISOTOPE TABLE 5 (Continued)
SUMMARY
OF RADIOACTIVEEFFLUENT RELEASES REPORTING PERIOD 0 NOVEMBER 1981 TO 30 DECEMBER 1981 TURKEY POINT - UNIT 3 RADIOACTIVITYRELEASED IN AIRBORNE EFFLUENTS
~
(CURIES)
NOVEMBER DECEMBER ll/5-12/2 12/3-12/30 TOTAL ACTIVITY TOTAL RELEASED THIS RELEASED DURING REPORTING S/G REPAIR PERIOD 'O DATE Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 TOTAL B.
HALOGENS 1-131 1-133 TOTAL
<<Not Detectable
0 t~
~ g
1981 TABLE 5 (Continued)
SUMMARY
OF RADIOACTIVEEFFLUENT RELEASES REPORTING PERIOD.0 NOVEMBER 1981 TO 30 DECEMBER 1981 TURKEY POINT-UNIT 3 I.
AIRBORNE RELEASES C.
PARTICULATES NOVEMBER DECEMBER ISOTOPE 11/5-12/2 12/3-12/30 RADIOACTIVITYRELEASED IN AIRBORNE EFFLUENTS (CURIES)
TOTALACTIVITY TOTAL RELEASED THIS RELEASED DURING REPORTING S/G REPAIR PERIOD TO DATE Ce-101 Ce-140 Co-58 Co-60 CS-134 Cs-137 Fe-59 Mn-50 Zn-65 Nb-95 0.0E-06 I.IE-05 6.7E-07 1.2E-06 4.8E-07 9.0E-OS 8.6E-06 1.2E-00 I
5.0E-07 2.3E-06 7.0E-08 1.26E-05 1.31E-00 1.17E-06 3.50E-06 5.50E-07 9.00E-OS 2.32E-05 1.67E-00 1.80E-06 7.83E-06 7.37E-07 1.15E-07 TOTAL "Not Detectable 1.70E-05 1.31E-00 1.09E-00 2.0IE-00
14
22 TABLE 6
SUMMARY
OF SOLID LOW-LEVELRADIOACTIVEWASTE REPORTING PERIOD 0 NOVEMBER 1981 TO 30'DECEMBER 1981 TURKEY POINT - UNIT 3 I.
SOLID LOW-LEVELRADIOACTIVE'WASTEGENERATED FROM U-3 S/G REPAIR WASTE FORM VOLUMELLWa IN CU-FT VOLUMELLW IN CU-FT FOR REPORTING PERIOD TO DATE Compacted Dry Active Waste Non-Compacted Dry Active Waste Resin and Filter Media Channel Head Decontamination Waste Miscellaneous Totals 5,670 675 025 85 200 7,055 10,605 0,030 1,020 717.5 2/775 19,107.5 II.
SOLID LOW-LEVELREPAIR ACTIVITYWASTE SHIPPED REPORTING PERIOD DATES VOLUMELLWa SHIPPED ESTIMATED ACTIVITYb IN CU-FT CURIES 20 3une 81 - 22 August 81 23 August 81 - 3 November 81 0 November 81 - 30 December 81 Totals 3,905 6,700 6,030 17,075 1.08 22.62 5.03 29.53 a LLW Low-level (radioactive) waste.
b Predominant isotopes 137Cs, 60Co, 58Co.
1