ML17345A989

Steam Generator Repair Program,Radiological Progress Rept 2 for 821203-830202

ML17345A989
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Site:	Turkey Point
Issue date:	03/10/1983
From:	FLORIDA POWER & LIGHT CO.
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STEAM GENERATOR REPAIR PROGRAM FOR TURKEY POINT UNIT 0 RADIOLOGICAL PROGRESS REPORT - NO. 2 FOR THE PERIOD DECEMBER 3, 1982 THROUGH FEBRUARY 2, 1983 DOCKET NO. 50-251 LICENSE NO. DPR-01 FLORIDA PO%'ER AND LIGHT COMPANY 8303i5032i 8303iOl PDR ADOCK 0500025i (

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TABLE OF CONTENTS PAGE NO.

1.0 INTRODUCTION

2.0 "OCCUPATIONAL RADIATION EXPOSURE 2.1 General 2.2 Description and Format of Exposure Data 2.3 Discussion of Exposure Results 3.0 APPLICATION OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES) 3.1 General 3.2 Temporary Shielding 3.3 Steam Generator (S/G) Water Level 5, 3.0 Contamination Control Envelopes and Ventilation 6 3.5 Decontamination of S/G Channel Heads 6 3.6 Flame and Machine Cutting Operations 8 3.7 Weld Preparation of S/G Channel Head Remnants 3.8 Installation of Steam Generator Lower Assemblies (SGLA's) 8 3.9 Transfer of Steam Generator Lower Assemblies to S/G Storage Compound 3.10 General Techniques and Practices 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 10 4.1 General 10 0.2 Liquid Releases 10 0.3 Airborne Releases 11 0.0 Solid Radioactive Waste 11

5.0 CONCLUSION

S AND OBSERVATIONS TABLES TABLE 1 Description of Major Tasks 13 TABLE 2 Personnel Exposure Summary - Per Task 15 TABLE 3A Summary of Preparatory Activity Exposures 17 TABLE 3B Summary of Removal Activity Exposures 20 TABLE 3C Summary of Installation Activity Exposures 23 TABLE 0 Personnel Exposure Summary - Per Phase 25 TABLE 5 Summary of Radioactive Effluent Releases 26 TABLE 6 Summary of Solid Low Level Radioactive Waste Shipments 29

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1.0 INTRODUCTION

Radiological Progress Report No. 2 contains information pertaining to the radiological aspects of the Unit 0 Steam Generator Repair Program (SGRP) for the period December 3, 1982 through February 2, 1983. 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:

Installation of channel head contamination control envelopes and absolute filter ventilation system.

2. Removal of main steam and feedwater piping.

3. Cutting and removal of steam generator upper assemblies.

Upending of S/G upper assemblies, placement in. rack and removal of secondary side internals.

Installation of steam generator lower assembly tube bundle shield covers.

6. Channel head decontamination (Alumina Grit-Blast method).

7. Cutting steam generator lower assembly channel heads and divider plates.

Rigging steam generator lower assemblies and installing tube sheet shield covers.

9. Removal of steam generator lower assemblies from reactor containment building and placement in S/G storage compound.

10. Preparation of channel head remnant for welding new steam generator lower assemblies.

11. Rigging new SGLA's into reactor containment building.

12. Installation of SGLA's (includes such operations as lower girth weld and channel head welding).

13. Installation of S/G upper assemblies (includes upper girth weld and installation of secondary side components).

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~ ~y 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, surveillance of temporary shielding, health physics support and project supervision.

2.0 OCCUPATIONAL RADIATION EXPOSURE 2.1 General As indicated in Radiological Progress Report No. 1, 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. 1. 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 p'eriod (i.e., from project commencement on 10 October 1982 to 2 February 1983).+ 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. 'xposures'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.

Ce 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.

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d. Task items indicating no accumulated exposures have not commenced during this reporting period.

A detailed summary of the personnel exposure expended through this reporting period for preparatory, removal and installation activities is presented in Tables 3A, 3B and 3C respectively. This summary includes both the labor and exposure expenditures

+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, accumulated dose is reported conservatively.

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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.

a. Activity status 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.

C. For completed activities it should be noted that small amount 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.

d. Some activities were not estimated in the SGRR and have no estimated labor and exposure values'indicated. These activities are controlled by RSVP's which have an exposure estimate for the activity for purposes of exposure "tracking".

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 02% of the original total estimate. Table 2 actual exposures are recorded by computer acquisition as discussed in Progress Report No. 1. Table 2 includes all exposure expended through February 2, 1983 and will continue to be used for accumulation of all personnel exposures through project completion. The exposure expended to date is primarily attributed to repair project preparatory, removal and installation activities as indicated in Tables 3A, 3B, 3C and0.

Tables 3A and 3B show that the total occupational exposure accumulated for completed activities to date is approximately 230 and 396 person-rem respectively as compared to their 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 is approximately 51%

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 251 person-rem as compar'ed to the original estimate of 600 person-rem.

The information for all phase activities in progress or completed (as shown in Tables 3A, 3B and 3C) is summarized in Table 0. Detailed exposure information for the installation and miscellaneous (post-installation) phase activities will be presented in subsequent reports. A discussion of expended exposures for the Unit 3 and Unit 0 SGRP and a summary of Unit 0 SGRP tasks where the reported person-rem expended is significantly greater than the estimated values will be presented in the final report for the Unit 0 SGRP.

3.0 APPLICATION OF DOSE REDUCTION TECHNI UES (ALARA PRINCIPLES) 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 data permits, the following evaluations include a quantitative 'vailable assessment of the person-rem savings which can be attributed to the techniques Usedo 3.2 Tem orar Shieldin The use of tempor'ary shielding and the exposure reductions expected through its application have been described in Progress Report No. 1. As of this reporting period the dose accumulated related to the installation of temporary shielding is approximately 11 person-rem (See table 3A, item 15). As indicated in Progress ~

Report No. 1, the original exposure estimate was approximately 2.0 person-rem.

This increase is primarily attributed to the additional shielding of high occupancy/traffic areas beyond the original expected, which should result in a significant reduction in exposure to personnel performing various activities due to the lower general area radiation fields. Such high occupancy/traffic areas where shielding was installed included the following:

a ~ 5S'levation

1. West end of refueling cavity opposite B S/G.

2. Pressurizer mini-spray lines outside pressurizer cubicle.

b. 10'levation

1. Let-down valve station outside biological shield wall.

2. Refueling cavity drain valves - outside biological shield wall.

3. Regenerative Heat Exchanger - inside biological shield wall.

A, B, R C RTD Loop Bypass lines - inside biological shield wall.

5. RHR piping - outside biological shield.

Temporary shielding was utilized during certain operations which would have resulted in elevated general area dose rates. Such operations included:

1. 0 eration of S/G channel head decontamination e ui ment.

Various components of the S G channel head grit decontamination system were shielded prior to installation to reduce dose rates in the vicinity of the decontamination equipment and the equipment hatch.

2. Transfer of alumina - rit from the RCB to the Radwaste Buildin .

The collection container for the used grit from S G channel head decontamination operations was located in the Radwaste Building adjacent

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to the Unit 0 Containment. The transfer piping from the RCB to the Radwaste Building was shielded to reduce exposure to personnel outside the equipment hatch during grit transfer operations. Typical dose rates at contact with the shielded transfer lines during grit transfer were approximately 20-50 mR/hr. General area dose rates were approximately 2-5 mR/hr.

3. Shieldin ersonnel monitorin stations durin SGLA removal from RCB.

Shielding was installed at the personnel monitoring stations in the Yuclear Maintenance Building (exit from RCA) to maintain acceptable background radiation levels for personnel frisking during the time that the SGLA's were being removed from the RCB and prepared for transfer to the S/G storage compound.

Temporary shielding was also installed in A, B, R C S/G channel head remnants after channel head decontamination and lower assembly removal. General area dose rates in the channel head remnants were reduced from levels of 0.2- 0.0 R/HR to .03 - .06 R/HR. The shielding designed included the capability of removing the shielding through the S/G manways after channel head welding and interior repair work is completed. The exposure expended for this activity is included in exposure totals for installation and welding of the SGLA's (See table 3C, item 3). Information pertaining to the exposure savings realized due to this shielding effort will be discussed in a future report.

A small amount of this exposure expended is attributed to daily surveillance checks of temporary shielding areas to verify that the temporary shielding is still in place and that exposure rates in the area have not significantly changed.

3.3 Steam Generator (S/G) Water Level Those repair project activities benefiting from the effect of maintaining a high water level in the S/G secondary included:

a) Installation of scaffolding in preparation of insulation removal.

b) Removal of insulation on shell assembly between 30'6 and 58'levation.

c) Removal of steam generator instrumentation lines.

d) Removal of reactor coolant pump motors.

e) Concrete cutting and removal in S/G cubicles and in upper girth cut area.

f) Layouts of upper and lower shell girthcuts and setting up of equipment.

g) 80% precision machine cut of S/G channel heads.

h) Installation of contamination control envelopes at channel head girth cut area.

i) S/G secondary moisture separator components removal.

j) Preparation and removal of S/G upper assembly.

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k) Removal of miscellaneous piping from S/G cubicles.

l) Installation of tube bundle shield cover.

The dose expended for the above completed tasks was approximately 150 person-rem. Without the benefit of secondary side watershielding the exposure expended would have been in the approximate range of 600 to 750 person-rem.

Thus a conservative exposure savings of approximately 050 person-rem was realized.

3.0 Contamination Control Envelo es and Ventilation The use of contamination control envelopes and filter'ed ventilation system proved effective during SGLA removal and installation for welding. S/G channel head and divider plate cutting operations as well as weld preparation activities were performed inside these enclosures. Airborne radioactivity levels in the enclosures were typically less than three times the maximum permissible concentration (iMPC) for the radionuclides detected while such activities were in progress. Personnel working in the enclosures were wearing appropriate respiratory protection devices and protective clothing during those operations.

iso significant airborne activity was detected outside the S/G enclosures that required either local evacuation and posting of the adjacent area or the use of respiratory protection devices. The S/G filtered ventilation system (as described in Radiological Progress Report bio. 1) effectively maintained a negative pressure in the work area thereby preventing the release of airborne radioactivity outside the channel head enclosures. All ventilated air is exhausted from the S/G enclosure filtered ventilation system through the containment ventilation exhaust system via the plant stack which is continously monitored "during discharge. Contamination control enclosures and ventilation will be utilized as necessary throughout SGLA installation activities.

Contamination containments were also utilized for various items and components removed from the reactor containment building and placed in temporary storage.

Several large containment enclosures were constructed and utilized for the overhaul of large components such as reactor coolant pump motors, manipulator crane motor and control rod drive cooler motors and fans. There containments require very little assembly/disassembly time and provide adequate control for work performed on items with low levels of contamination (generally less than 5000 dpm/100cm2).

3.5 Decontamination of S/G Channel Heads S/G channel head decontamination (Alumina-grit blast method) was also completed during this reporting period. As shown in table 3B, item 5, the personnel exposure expended for this effort was approximately 91 person-rem.

The exposure estimated for this task was 210 person-rem. The equipment used was designed to minimize occupancy times in high exposure areas by allowing extensive remote operation. The temporary manway cover was constructed with quick-disconnect hoses and electrical connections to minimize working time at the manway. The equipment utilized was upgraded since the Unit 3 SGRP to improve reliability and system performance.

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As determined from the Unit 3 SGRP channel head dose rate measurements (regarding surface decontamination factors ) two grit passes were made in each channel head. Channel head decontamination also included decontamination of the S/G manway openings. Special grit-blast tooling was developed to decontaminate the manway openings which proved highly successful. These manway openings were not decontaminated during the Unit 3 SGRP which resulted in a general area dose rate of approximately I R/HR for personnel.

passing through the manway. The decontamination of the S/G manway openings during the Unit 0 SGRP resulted in general dose rates of approximately .25 R/HR. This effort will further serve to reduce personnel exposure for channel head activities.

Experience has shown that. approximately 00% of the'S/G channel head dose rate is attributed to the tube sheet. Prior to decontamination dose rates in the channel head center averaged approximately 8.5 R/HR. This indicates that a dose rate of approximately 5 R/HR would be expected in the channel head remnant after removal of the lower assembly (including tubesheet). With the removal of the steam generator lower assembly, the major contributing source of exposure in the S/G channel head remnant was the inlet and outlet nozzle openings. Channel head general area dose rates after grit-blasting and nozzle shielding were approximately 0.2 R/HR" This indicates that an effective dose reduction factor of approximately 25 was obtained.

The following activities have benefited from decontamination of the channel heads:

a. Removal of inflatable nozzle seals.'.

Installation of shielded nozzle seals.

c. Installation o'f special channel bowl shielding.

d. Marking and cutting of divider plates.

e. Inspection of loops and nozzle seal areas.

f. Weld preparation of channel head remnants.

The exposure expended for these activities to date is approximately 20 person-rem. The actual overall exposure savings realized to date as a result of channel head decontamination and shielding is approximately 290 person-rem. The following tasks are yet to be completed and are also expected to have the benefit of channel head decontamination and shielding:

a. Interior channel head and divider plate welding activities.

b. Channel head Q.C. inspections.

c. Miscellaneous clean-up and closeout activities.

Assessment of the exposure savings attributed to channel head decontamination and shielding will be made in subsequent reports after all activities associated with this effort are completed.

pt 3.6 Flame and Machine Cuttin 0 erations The steam generator upper assemblies were cut using a flame technique. This method svas extremely fast and efficient and produced no significant airborne radioactivity. The exposure expended for the S/G upper assembly girthcut was approximately 3 person-rem (See table 31, item 6). The exposure estimate for this activity was approximately 33 person-rem.

A, B, R C S/G channel head (lower girth) cuts were performed using precision maching cutting equipment. The exposure expended for S/G A, B, R C channel head cutting was approximately 22 person-rem as compared to the estimate of approximately 60 person-rem. No significant airborne radioactivity was detected during channel head precision machine cutting operations.

The A, 8, 2 C S/G divider plates were flame cut using remotely operated equipment. The exposure expended for this activity was approximately 0 person-rem as compared to the estimate of approximately 3.5 person-rem (See table 3B, item 10).

In general, no significant airborne radioactivity levels were detected in the enclosure during channel head cutting and divider plate cutting operations. A discussion of the exposures expended for Unit 0 SGRP machine and flame cutting operations and the Unit 3 SGRP exposures for the same activities will be presented in the final progress report for the Unit 0 SGRP..

3.7 Weld Pre aration of S/G Channel Head Remnants Weld preparation of the S/G channel head remnants were completed during this reporting period. To minimize exposure during machine weld preparation of the channel head, a remotely operated machine tool was utilized as much as practical. The installation of nozzle shielding also served to reduce general area dose rates to personnel conducting the channel head weld preparation. A contamination control enclosure with filtered ventilation system was utilized to control airborne radioactivity and confine the spread of contamination during weld preparation. Airborne radioactivity levels were generally less than the maximum permissable.concentration (MPC) for the principal radionuclide detected - Cobalt 60. The exposure expended for this activity was approximately 13 person-rem as compared to the estimate of approximately 8 person-rem (See table 3C, item 2).

3.8 Installation of Steam Generator Lower Assemblies (SGLA's)

Installation of the new SGLA's commenced during this reporting period. Once the new steamgenerator lower assemblies were fit to the channel head remnant, access'to continue weld preparation and welding was directed to the S/G manways. To minimize personnel exposures on the S/G platforms, access/egress to the S/G work platforms is controlled from outside the biological shield wall where dose rates are typically ten times less than dose rates inside the shield wall. The weld technique for the lower girth weld was revised and approved resulting in reduced personnel time inside the channel head to complete lower girth welding.

A contamination enclosure was installed at the S/G manways to minimize airborne radioactivity in the vicinity of the platform and confine the spread of contamination during weld preparation and welding. Access/egress to the

channel head is conducted through the coldleg S/G manway with an absolute filtered ventilatiori blower exhausting from the hotleg manway. This is made possible since a section of the divider plate was removed to support stress relieving and weld operations thus permitting access to the entire channel head.

Required service leads and hoses are routed through the manway ventilation attachment. This serves to keep the cold leg manway free of the hoses and leads which would impede access/egress to and from the channel head area. Since the welding of the channel head and divider plate require preheating, temperatures in the channel head are generally greater than 100oF. To provide some relief, ventilation duct work with cool air has been directed to the cold leg manway opening allowing the cool air to be drawn into the channel head work area. The air is then exhausted through the S/G filtered ventilation system and containment ventilation exhaust system. As stated earlier the normal containment ventilation exhaust system is continuously monitored during discharge.

As discussed in Section 3.2, special channel head shielding is utilized for interior.

channel head welding and repair work whenever practical to reduce personnel exposure.

The exposure expended to date for channel head welding activities is approximately 108 person-rem as compared to the estimate of 192 person-rem (See table 3C, item 3).

A summary of the exposures expended for welding of the channel head and divider plates will be discussed in future reports.

3.9 Transfer of Steam Generator Lower Assemblies to S/G Stora e Com ound The SGLA's were removed from the reactor containment building and placed in the storage compound during this reporting period. The exposure expended for this activity was approximately 6 person-rem as compared to the estimate of 25 person-rem (See table 3B, item 13).

Surveys taken outside the S/G storage compound after placement of the SGLA's indicated approximately 0.1 to OA mR/hr contact with the walls and, approximately 25 to 35 mR/hr contact with the roof of the storage compound. It should be noted that the S/G storage compound is located in the RCA and now contains the Unit 3 and Unit 0 SGLA's (a total of six).

3.10 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.

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10 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. l.

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) A communications system used by Health Physics personnel 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.

1) Increased frequency of TLD readouts for purposes of obtaining actual exposure information for personnel working in the S/G channel heads and other relatively high exposure areas.

Quantitative assessments are difficult to develop for these "general" techniques and practices which contribute significantly to the overall ALARAcommitment for the repair project. An update on these techniques and practices will be discussed in future reports.

0.0 RADIOACTIVE EFFLUENTS AND SOLID IVASTE 0.1 General Radioactive effluents, comprised of liquid and airborne releases, and low-level solid radioactive waste produced during this reporting period and throughout the repair project to date are summarized in Tables 5 and 6 respectively.

R Laundry operations continue to be the major volume of liquid releases for the Unit 0 SGRP. As shown in Table 5 the composition of radioactive isotopes detected remain relatively unchanged from those detected during.,the previous period. Approximately 36% of the total activity released to date (excluding tritium) was in the form of activated metals (e.g. Co-58, Co-60, Mn-50, Ag-.

110m). the remaining activity (excluding tritium) included the following radionuclides: Cs-137 (21%), Cs-130 (12%), Cs-136 (0.3%) and radioiodines (31%).

The total activity released (excluding tritium) to date is approximately 12% of the activity projected to be released for Unit No. 0 during the repair project (refer to Table 5.2-7 of the SGRR). The amount of tritium which has been released from SGRP activities, remains approximately 25% of the amount that

.was estimated (Table 5.2-7 of the SGRR).

11 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. The particulates detected are typical of radionuclides expected as a result of an extended shutdown. The total activity released to date that is attributed to repair project activities is approximately

'18% of the total estimated activity projected to be released.

0.0 Solid Radioactive Waste A summary of low level radioactive waste (LLW) shipments from Unit 0 during the reporting period is provided in Table 6. The amount of LLW which had been packaged but not shipped prior, to the close of the period is also provided. The LLW shipments during this reporting period were made to both the Barnwell, South Carolina and Richland, Washington Low-Level Waste Disposal Facilities.

The majority of the waste volume shipped was compactable and non-compactable dry active waste.

The total volume of solid LLW generated due to repair project activities through this reporting period (excluding the SGLA's) is approximately 86% of the total volume estimated in the Gould Affidavit dated 3une 12, 1981. It should be noted that the volume of waste shipped is less than the accumulated volume of waste generated. This can be primarily attributed to additional volume reduction techniques used prior to shipmen't, which are not accounted for when initially generated. The total quantity of radioactivity shipped through this reporting period as a result of the Unit 0 SGRP was less than 06% of the activity estimated in the SGRR. The remaining LLW generated is expected to be expeditiously shipped to a licensed burial facility.

5.0 CONCLUSION

S AND OBSERVATIONS With the preparatory and removal phase activities completed, the actual total exposure expended for these activities was significantly lower than the original estimated exposure (i.e. approximately 626 person-rem versus 1299 person-rem respectively). The total exposure expended for the preparatory and removal phase activities is approximately 51% less than the estimated exposure and approximately 22% less than the Unit 3 SGRP actual exposure for the preparatory and removal phase.

The actual exposure expended for installation phase activities through this reporting period is approximately 251 person-rem as compared to the estimate of 600 person-rem. Approximately 08% of the actual exposure expended for installation phase activities is attributed to weld preparation of the S/G channel head remnants and S/G lower girth and interior channel head welding. With the S/G lower girth weld essentially completed, the remaining exposure to be accumulated should be the result of interior channel head welding (i.e. cladding.)

The trend of lower expended exposure for activities reported is expected to continue throughout the Unit 0 SGRP.,Subsequent reports will provide updates on this exposure trend.

~ I 12 Table 0 shows that the actual labor expended to date is approximately 82% of the total labor estimate projected for the Unit 0 SGRP. Since a significant amount of installation and post-installation phase activities remain to be completed, it is expected that the total actual person-hours for the project will be somewhat higher than the total estimated labor value for the Unit 0 SGRP.

This higher actual expended labor value can be attributed to the uncertainties in predicting labor expenditures for the repair project as discussed in section 3.3.7-2 of the SGRR.

a) Radioactive liquid effluents released are well within the total estimate projected to be released in Table 5.2-7 of the repair report. The calculated activity (excluding tritium) is approximately 12% while the tritium activity is approximately 25% of the total estimated activity in the SGRR.

b) Airborne releases of radioactivity attributed to repair project activities are below the estimates provided in the SGRR. The activity associated with airborne releases for the remaining portion of the repair project is expected to decrease as the project progresses. The airborne activity discharged through the entire repair effort is not expected to exceed the estimate indicated in the SGRR.

c) Solid low level radioactive waste generated to date (excluding the SGLA's) for the Unit No. 0 SGRP represents approximately 86% of the estimate provided in the Gould Affidavit dated 3une 12, 1981.,Some conservatism is employed in assigning the volume of waste generated to the Unit 0 SGRP even though some of the work was not directly relat'ed to the repair project. The total quantity of radioactivity shipped was significantly below the activity estimated in the SGRR.

-In order to coincide with the routine monthly preliminary radioactive effluent release reports generated at the plant site, progress report number 3 will contain information from February 2, 1983 through March 30, 1983.

13 TABLE 1 DESCRIPTION OF MA3OR TASKS TASK TASK DESCRIPTION

1. Concrete and structural This task includes all work associated steel removal and with removal/replacement of concrete placement. 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 2. This task includes installation/removal of cranes, preparation of the pedestal crane foundations, assembly polar crane, miscellaneous and erection of cranes and the polar crane cribbing platforms, S/G tr'olley, and disassembly and removal of transfer bridge. . cranes and the polar crane trolley.

3. Removal, modification and 3. Items included in this task are: Erection/

reinstallation of S/G removal of scaffolding from El 58'o upper assemblies and El 93', removal/installation of insulation major piping. 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 The major exposure items in this task are:

facilities and support Routing of welding leads, installation of services. 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.

5. General decontamination and 5. This task includes'general area disposal of contaminated decontamination of the containment prior materials/cleanup. to commencement of major work, continuous containment decontamination for the entire outage, and removal and disposal of contaminated material for the entire outage.

TABLE 1 (continued)

DESCRIPTION OF MA3OR TASKS TASK TASK DESCRIPTION

6. Removal and reinstallation 6. This task includes removal of insulation of miscellaneous piping, from the steam generator and main steam equipment and insulation. and feedwater piping, installation of insulation on the new steam generators, and removal/installation of miscellaneous items.

7. Non-manuals (e.g., QC, 7. The non-manual category includes health Engineers, HPs). physics, quality control, and engineering personnel, visitors, and Bechtel personnel required for the entire outage.

8. Decontamination of the Included in this task are mechanical grit channel head. blast decontamination of the channel head, and installation of inflatable plugs in the reactor coolant piping.

9. Cut channel head and remove 9. This task includes installation of tenting old S/G lower assembly. and temporary shielding, cutting the transition cone, and channel head, and rigging and removal of the lower assembly to the containment equipment hatch.

10. Weld shield cover on lower 10. The only item in this task is welding of assembly. steel plates at each end of the steam

a. At channel head generator to provide shielding and to

b. At transition end prevent leakage.

Cut and remove old divider 11. The divider plate was detached from the plate, weld new divider tubesheet as part of Task 9. Removal and plate. placement of the divider plate to the channel head is included in this task.

12. Install new S/G, weld 12. This task includes erection/removal of channel head. 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.

13. Placement of steam 13. This task includes transporting of the S/G generator in storage. from the containment equipment hatch into the storage compound and construction of a roof once the S/G's are in the compound.

I I I

15 TABLE 2 PERSONNEL EXPOSURE

SUMMARY

PER TASK REPORTING PERIOD 10 OCTOBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 0 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSUREa (PERSON-HOURS) (PERSON-REM)

TASK DESCRIPTION ESTIM ATED ACTUAL ESTIMATED ACTUAL

1. Concrete and structural steel 13,660 16,652 88 50.78 removal and replacement.

2. Construction of pedestal 10,280 1,908 32 4.63 cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.

3. Removal, modification and 20,600 25,551 256 109.63 reinstallation of steam generator upper assemblies and major piping.

0. Construction of temporary 19,120 22,930 215 55.53 facilities and support services II

5. General decontamination and 02) 310 28,089 201 126.29 disposal of contaminated materials/cleanup.

6. Removal and reinstallation of ,8,850 11,300 125 81.18 miscellaneous piping equipment and insulation.

7. Non-manuals (e.g. QC, 68,500 20)817 036 100. Ol Engineers, Health Physics).

S. Decontamination of the 1,800 5,507 210 90.71 channel head.

9. Cut channel head and remove 3)200 0,898 166 05.59 old steam generator lower assembly.

10. Veld shield cover on lower assembly:

a. at channel head 760 1,120 00 16.39

b. at transition end 530 916 53 10.82

I I I'I

~ I

16 TABLE 2 (continued)

PERSONNEL EXPOSURE

SUMMARY

- PER TASK REPORTING PERIOD 10 OCTOBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT UNIT 0 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSUREa (PERSON-HOURS) (PERSON-REM)

TASK DESCRIPTION ESTIMATED ACTUAL ESTIMATED ACTUAL

11. Cut and remove old divider 2,600 302 29 3.60 plate, weld new divider plate.

12. Install new steam generator 11,000 20,891 200 127.35 weld channel head.

13 Placement of steam generator 225 200 25 6.10 in 'storage.

TOTAL 207,595 169,569 2,080 877.09 Estimated Range 1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.

I TABLE 3A

SUMMARY

OF PREPARATORY ACTIVITY EXPOSURES REPORTIHG PERIOD 3 DECEMBER 1982 to 2 FEBRUARY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPEHDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TQ-DATE (C-COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON-REM) (PERSON-REM) (I-IN PROGRESS)

1. Initial Containment Decontamination. 4,816 3,276 45.00 0.00 18.39

2. Reactor Cavity Decontamination. 0 162 Q.OQ 0.23 1.51

3. Reactor Cavity Liner Plate Inspection. 300 0.00 6.04 6.04 Install 8/G Transfer Bridge. 960 147 '1.21 0.00 0 '9

5. Remove Emergency Containment Coolers'.

140 78 1.68 0*00 0.24 Remove CRDM Coolers snd Fans. 67 215 0.28 0.00 1.34

7. Rerate Polar Crane and Load Test. 4,571 1,481 9.49 0*02 2.97

&. Disassemble Manipulator Crane and Store. 128 0.00 0.11 0. 91

9. Install Cherry Pickers. 2s430 266 6.06 0.00 1.35

10. Remove Reactor Coolant Pump Motors. 397 0.00 0.00 2.59

y ~ k J TABLE 3A (Continued)

SUMHARY OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 DECEHBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIHATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REH) (PERSON-REH) (PERSON-REH) (I-IN PROGRESS) ll. Disconnect/Remove Permanent Electrical Equipment and Cables. 430 304 1.93 0.00 0.79

12. Install Temporary Power, Lighting

'nd Electrical Items. 1,148 4,458 49.50 0.00 18.55

13. Remove Miscellaneous Steel. 580 3,532 6.21 1.10 8.20

14. Install/Maintain S/G Temporary Containments and Ventilation. 1,008 1,013 17.63 1 ~ 70 2.92

15. Install Temporary Shielding. 120 1,193 2.38 0.00 11 '7

16. Install Scaffolding-all levels. 1,440 5)203 3.31 0.00 34.19

17. Cut and remove concrete 30'6 and 58'levation. 5,334 4,173 52 '0 0.00 38.91

18. Project non-manual support. 6,927 7,207 60.00 0.00 35.57 19 ~ On"going Decontamination Activities. 1,204 1,092 8.19 0.00 6.13

~ ~

TABLE 3A (Continued)

SUMMARY

OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 DECFMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON"REM) (PERSON-REM) (I-IN PROCRESS)

20. Containment Tool and Weld Rod Room Support. 1,232 506 7.55 0.00 0.35 C

21. Remove/dispose of contaminated materials. 900 3,009 E 7,41 0.00 18.64

22. Crane operation/maintenance. 685 31722 1.36 0.00 7.63

23. Miscellaneous Activities, 1,000 7,560 1.51 0.22 11.21 Total Phase I 34,992 49,422 283 9.42 229.99

)

I 1 0 II

TABLE 3B

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR FXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-BOURS) (PERSON-BOURS) (PERSON-REM) (PERSON"REM) (PERSON-REM) (I-IN PROGRESS)

1. Remove insulation from Ai B~ & C S/C's. 3,500 61721 . 77.00 0.02 63.64

2. Remove feedwater piping A~ B~ & C S/G's. ,147 2,932 1.50 7.29 10.76

3. Remove main steam piping A~ B, & C S/C's. 125 331 0.61 0.60 1.76

4. Remove miscellaneous piping from A, B, & C S/C .cubicles. 1,410 1,370 17.62 10.92 18.11

5. Conduct channel head decontamination A, B, & C S/C's.

d.

1,835 5,547 214.00 82.54 90.71

6. Cut A, B, & C S/G upper assemblies. 630 683 33.30 2.65 2.88

7. Lift A, B, & C S/C upper assemblies, invert and place in racks. 525 -1,575 6.75 7.59 7.74

8. Cut A, B~ & C S/G channel heads. 714 2,115 60.24 8.52 22.33

9. Install tube bundle shield covers A, B, & C S/G's. 525 916 53.00 14.79 14.82

TABLE 38 (Continued)

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTIHG PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR RFPORTING EXPENDED STATUS ACTIVITY DESCRIPTIOH LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON"HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON-REM) 'PERSON"REM) (I-IN PROGRESS)

10. Cut A, B & C S/G divider plates. 252 317 3.36 3.64 3.64 ll. Lift A, 8 & C SGLA, cut and remove seismic rings. 1,089 221 77.16 2.65 3.59

12. Install tube sheet shield covers A, B & C S/G's. 755 1,124 .40.00 16.39 16.39

13. Remove A, 8 & C SGLA's from reactor containment building and place in storage compound. 225 200 25 F 00 6.14 6.14

14. Maintain temporary power, lighting & electrical items. 2, 100 2i793 55.00 5-93 5.93

15. Maintain, erect, and remove scaffolding. 840 7,308 8.40 22.93 31.47

16. On going decontamination activities. 10,900 2I540 32. 76 12.74 12.74

17. Rcmove/dispose of contaminated materials. 3,600 7,617 29.62 19.01 37.65

TABLE 38 (Continued)

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TQ DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON-REM) (PPRSON-REM) (I-IN PROGRESS)

18. Project non-manual support. 271725 6,410 214.72 24.58 24.58

19. Containment tool and weld rod room support. 840 39 2 ~ 52 0.09 0.09

20. Crane operation and maintenance. 3,015 2,334 5.44 4.05 4+05

21. Miscellaneous Activities. 8,377 1,364 58.00 10.79 16.60 Total - Phase II 69,129 54,457 11016 263.86 395.62

TABLE 3C

SUMMARY

OF IHSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTIHG EXPEHDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON"REM) (PERSON-RKM) (PERSON-REM) (I-IN PROCRKSS)

1. Remove S/G upper assembly internals and install/modify A, B and C S/G secondary internal components. lls260 6,283 93.10 14.01 14.01

2. Weld preparation of A, B & C S/C channel head remnants. 840 1,755 7.71 12.69 12.69

3. Install/weld A, B & C SCLA's (includes post~old heat treatment). 8,696 14s344 191.64 107.97 107.97

4. Install/veld A, B & C S/C divider plates. 1,554 15.10 0.00 0.00

5. Install/weld A, B' C S/C upper assemblies. 6,280 5,602 23.82 8.92 8.92

6. Installation of A, B & C S/G main steam piping. 1,250 649 5.50 1.48 1.48

7. Installation of A, B & C S/G feedwater piping. 1,680 273 6.80 0.66 0.66

8. Install insulation A, 8 & C S/G's. 3,486 29.40 0.00 0.99

9. Maintain temporary pover, lighting and electrical items. 2,850 4,327 65.00 11.11 11.11

TABLE 3C (Continued)

SUMMARY

OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTLHG EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C"COMPLETE)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON-REM) (PERSON-REM) (I-IH PROGRESS)

10. Maintain/erect/remove scaffolding. 2,840 7,355 20.67 23.42 23.42

11. Qn-going decontamination activities. 10,920 2,260 32.76 7.05 7.05

12. Remove/dispose of contaminated materials. 3,600 5,945 29.62 2,0.62 20.62 f

13. Project non-manual support. 14,460 10I024 86.27 29.97 29.97

14. Containment Tool & Weld rod room 'support. 840 196 2.52 0.35 0.35

15. Crane operation/maintenance. 2,740 2p344 5.43 1.78 1.78

16. Miscellaneous activities. 8,704 4,333 28.66 11.45 11.45 Phase Activity Totals 82,000 65;690 644 251.48 251.48 Total Phase III (Completed Tasks Only) 12,100 8,038 100.81 26.70 26.70

g i l I )

TABLE 4 PERSONNEL EXPOSURE SUMHARY PER PHASE REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT UNIT 4 TOTAL ESTIMATED ACTUAL EXPOSURE PHASE STATUS PHASE ESTIMATED LABOR ACTUAL LABOR ESTIMATED EXPOSURE FOR REPORTIHG ACTUAL EXPOSURE (C-COMPLETE)

DESCRIPTION EXPENDED TO-DATE EXPENDED TO-DATE EXPOSURE EXPEHDKD TO-DATE PERIOD EXPENDED TO-DATE (I-IN PROGRESS)

(PERSON-HOURS) (PERSON-HOURS) (PERSON-REM) (PERSON-REM) (PERSON-REM) (PERSON-REM) (HS-NOT STARTED)

Preparation 34,992 49,422 283 283 9.42 229.99 Removal 69,129 54,457 1,016 1~016 263.86 395.62 Installation 82,000 65,690 644 644 251.48 251.48 Miscellaneousa NS 141 0 0 Project totals 186,121 169,569 2)084 1,400 524.76 877.09 (Completed Phases Only) 104,121 103,879 1,299 1,299 625.61 aMiscellaneous (post-installation) - includes cleanup, storage and miscellaneous preparations prior to start-up.

I L ~

( ~ >

y

TABLE 5

SUMMARY

OF RADIOACTIVE EFFI UFNT RELEASES REPORTING PERIOD 2 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 1982/1983 I. LIQUID EFFLUENT RADIOACTIVITY RELEASED IN LIQUID EFPLUENTS RELEASES (CURIES)

TOTAL ACTIVITY TOTAL RELEASED THIS RELEASED DURING DECEMBER JANUARY REPORTING S/G REPAIR RADIOHUCLIDE 12/1 12/29 12/30 2/2 PERIOD TO DATE Ag-110m 1.09E"04 1.09E-04 2.39E-04 Co-58 2.53E-03 2.54E-03 5.078-03 1.06E-02 Co-60 3.17E"03 3.71E-03 6.88E-03 1.30E-02 Cs-134 8.55E-04 1.04E"03 1.90E-03 7.93E-03 Cs-136 1.90E-04 Cs-137 1 ~ 67K-03 1.988-03 3.65E-03 1.46E"02 I-131 4.52E-04 4.528-04 1.79E"02 I-133 2.508-03 I-135 2.60E-04 Mn-54 3.25E-05 3.258-05 1.038-04 Nb"95 7.55E-05 7.55E-05 7.558-05 TOTAL 8.68E-03 9.49E-03 1.828-02 6.74E-02 Tritium Released (Curies) 0.0 0.0 0.0 4.7E+01 VOLUME RELEASED VOLUME RELEASED Liquid Effluent Volume THIS REPORTING DURING S/G REPAIR Released (Liters) PERIOD TO DATE 1.23E+06 1.49E+06 2.72E+06 6,02Et06

• Not etectabie

TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVE EFFLUFNT RELFASES REPORTING PERIOD 2 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UHIT 4 1982/1983 I, AIRBORNE RADIOACTIVITY RELEASED IN AIRBORNE EFFLUENTS RElEASES (CURIES)

TOTAL ACTIVITY TOTAL A. NOBLE GASES RELEASED THIS RELEASED DURING DECEMBER JANUARY REPORTIHG S/G REPAIR RADIONUCLIDE 12/2 - 12/29 12/30 - 2/2 PERIOD TO DATE Ar-41 3 '2E-01 Kr-85 4.09E-01 Kr-85m 2.23E-01 Kr"88 1.39E-01 Xe-131m 1.37Ei00 Xe"133 8.62E402 Xe-133m 3.89E+00 Xe"135 6.59E+00 TOTAL 8.75E+02 TRITIUM 2.65E"02 B. 'HALOGEHS Br-82 1.90E"04 I-131 4.6E-03 4.6E"03 3.308-02 I-133 5 '28-03 TOTAL 4.6E-03 4'.6E-03 3.888-02

• Not Detectable

4.

s l

~ t

TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVF. EFFI.VENT RELEASFS REPORTING PERIOD 2 DFCFMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 4 1982/1983 I. AIRBORNE RADIOACTIVITY RELEASED IH AIRBORNE EFFLUENTS REI.EASES (CURIES)

TOTAL ACTIVITY TOTAL C. PARTICULATES RELEASED THIS RELEASED DURING DECEMBER JANUARY REPORTING S/G REPAIR RADIONUCLIDE 12/2 12/29 12/30 - 2/2 PERIOD TO DATE Ba-140 2.00E-05 Co-57 3.50E"07 Co-58 4.20E-05 3.408-05 7.60E-05 3.388-04 Co-60 4.308-05 5.608-05 9.908-05 1.698-04 Cr-51 1.208-05 Cs-134 4.30E-06 4.30E-06 1.018-04 Cs-136 3.548-05 Cs-137 1.108-05 7.30E-06 1.83E-05 1.978-04 I-131 3.108-05 3.108-05 1.04E-04 LQ-140 1.408-05 Mn-54 1.00E-06 3.00E-06 4.008-06 1.84E-05 Hb"93 3.10E-06 Ru-103 3 '0E-06 TOTAL 1.32E-04 1.00E-04 2.32E-04 1.02E-03

• Not Detectable

PC I y U

C

29 TABLE 6

SUMMARY

OF SOLID LOW-LEVEL RADIOACTIVE WASTE REPORTING PERIOD 3 DECEMBER 1982 TO 2 FEBRUARY 1983 TURKEY POINT - UNIT 0 I. SOLID LOW-LEVEL RADIOACTIVEWASTE GENERATED FROM U-0 S/G REPAIR WASTE FORM VOLUME LLWa IN CU-FT VOLUME LLW IN CU-FT FOR REPORTING PERIOD TO DATE Compacted Dry Active Waste 6,773 15,656 Non-Compacted Dry Active Waste 925 2,150 Resin and Filter Media 519 1,039 Channel Head Decontamination Waste. 595 '595 Miscellaneous Totals 8,812 19,000 II. SOLID LOW-LEVEL REPAIR ACTIVITY WASTE SHIPPED REPORTING PERIOD VOLUME LLWa SHIPPED ESTIMATED ACTIVITY DATES IN CU-FT CU RIES 10 October 82 - 2 December 82 7,191 0. 332 3 December 82 - 2 February 83 8,217 120.250 Totals 15,008 120.582 a LLW Low-level (radioactive) waste.

Predominant radionuclides 137Cs, 60Co, 58Co.

nip