ML17345B173

Steam Generator Repair Program for Turkey Point Unit 4, Final Radiological Progress Rept 4 for 821010 - 830516

ML17345B173
Person / Time
Site:	Turkey Point
Issue date:	07/15/1983
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17345B172	List: ML17345B171 ML17345B173
References
NUDOCS 8307220523
Download: ML17345B173 (61)

Text

STEAM GENERATOR REPAIR PROGRAM FOR TURKEY POINT UNIT 0 FINAL RADIOLOGICALPROGRESS REPORT - NO. 0 FOR THE PERIOD OCTOBER 10, 1982 THROUGH MAY 16, 1983 DOCKET NO. 50-251 LICENSE NO. DPR-01 FLORIDA POWER AND LIGHT COMPANY 8307220523 8307i5 PDR ADOCK 0500025i R PDR

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TABLE OF CONTENTS PAGE NO.

1.0 INTRODUCTION

2.0 OCCUPATIONAL RADIATIONEXPOSURE 2.1 General 2.2 Description and Format of Exposure Data 2.3 Discussion of Exposure Results 2.0 Summary of Major Tasks with Significant Expended Exposure 3.0

SUMMARY

OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES) 0 3.1 General 3.2. Temporary Shielding 3.3 General Containment Decontamination 5 3A Steam Generator Water Level 5 3.5 Contamination Control Envelopes and Ventilation 5 3.6 Concrete Cutting Operations 6 3.7 Channel Head Decontamination and Shielding 6 3.8 Flame and Machine Cutting Operations 7 3.9 Weld Preparation of S/G Channel Head Remnants 8 3.10 Installation of Steam Generator Lower Assemblies (SGLAs) 9 3.11 Welding of Steam Generator Divider Plates 10 3.12 Reactor Head Preparation for Hot Functional Testing 10 3.13 Steam Generator Storage Compound 10 3.10 General Techniques and Practices ll 3.15 Discussion of Unit 0 SGRP Lower Expended Exposure 11 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 12 0.1 General 12 0.2 Liquid Releases 12 0.3 Airborne Releases 12 0.0 Solid Radioactive Waste 13

5.0 CONCLUSION

S AND OBSERVATIONS 13

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TABLE OF CONTENTS PAGE NO.

TABLES TABLE 1 Description of Major Tasks 15 TABLE 2 Personnel Exposure Summary Per Task 17 TABLE 3A Summary of Preparatory Activity Exposures 19 TABLE 3B Summary of Removal Activity Exposures 22 TABLE 3C Summary of Installation Activity Exposures 25 TABLE 3D Summary of Post-Installation Activity Exposures 27 TABLE 0 Personnel Exposure Summary Per Phase 30 TABLE 5 'ummary of Radioactive Effluent Releases 31 TABLE 6 Summary of Solid Low Level Radioactive Waste Shipments 30

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1.0 INTRODUCTION

Radiological Progress Report No. 0 contains information pertaining to the radiological aspects of the Unit 0 Steam Generator Repair Program (SGRP) from project commencement 10 October 1982 through project completion 16 May 1983. This information includes the following:

ao 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).

Co An estimate of the radioactivity released in liquid and airborne effluents.

d0 An estimate of the solid radioactive waste generated including volume and radioactive content.

e. A summary for those tasks where actual person-rem expended was signifi-cantly greater than the estimated values and a discussion for the higher expended exposure.

A discussion of the Unit 0 SGRP lower expended exposure as compared to the Unit PE3 SGRP.

g>> A discussion of recommended changes in techniques to be evaluated to determine their effects on further lowering exposure for steam generator replacement-channel cut method.

Significant project tasks performed during the final reporting period (31 March, 1983 through 16 May, 1983) included:

1. Installation of miscellaneous steel.

2. Installation of manipulator crane.

3. Hot functional testing.

Cleanup activities (removal of scaffolding and support equipment, removal of temporary shielding, etc.).

2.0 OCCUPATIONAL RADIATIONEXPOSURE 2.1 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 was discussed in detail in Section 2.1 - 2.3 of Radiological Progress Report No. I. This program was utilized throughout the entire project.

A description of the thirteen (13) major tasks is indicated in Table 1.

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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 from project commencement on 10 October 1982 to project completion 16 May 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. 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 was utilized to "track" exposure for the time period of interest.

A detailed summary of the personnel exposure expended (for the entire project) for preparatory, removal, installation and post-installation activities is presented in Tables 3A, 3B, 3C and 3D 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.

2.3 Discussion of Ex osure Results A review of the data presented in Table 2 shows that the total occupational radiation exposure expended for all major tasks throughout the entire project was significantly below the estimated range of 1,730 - 2,080 person-rem. These exposures were recorded by computer acquisition as discussed in Progress Report No. l. A summary for the tasks indicated in Table 2 where actual person-rem expended was significantly greater than the estimated values and a discussion for the higher expended exposure is presented in Section 2.0.

Tables 3A and 3B show that the total actual exposure expended for preparatory and removal phase activities was approximatley 5196 less than the total estimated exposure for those activities.

<<Self-reading pocket dosimeter (SRPD) results were used to report person-rem since exposure information was immediately available upon exit from the RCA and accordingly recorded in the computer data base. Since thermoluminescent dosimeters (TLD's) were processed primarily on a monthly basis this information was not 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.

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Table 3C shows that the total exposure accumulated for installation phase activities was approximately 563 person-rem as compared to the original exposure estimate of 600 person-rem.

Table 3D shows that the total occupational exposure accumulated for post-installation activities was approximately 117 person-rem as compared to the original total estimate of 101 person-rem. Some of these activities (items 8, 9, 10, 11, and 12 of table 3D) were not included in the original estimate. These activities resulted in an exposure of approximately 06 person-rem.

Table 0 contains summarized information for all project phases (detailed in tables 3A, 3B, 3C and 3D). The total exposure expended (by SRPD) during the final reporting period (31 March 1983 through 16 May 1983) was approximately 61 person-rem. The total exposure expended for the Unit 0 SGRP was approximately 1305 person-rem (by SRPD).

2.0 Summar of Ma'or Tasks with Si nificant Expended Ex osure Both estimated and actual total labor and exposure expended for the 13 major

'tasks described in table 1 are shown in table 2. The following discussion presents a,summary of those tasks where the person-rem expended was significantly greater than the estimated values. Tables 3A through 3D are appropriately referenced for specific detailed job activities (RWP controlled) within a major task.

1. Task Nll - Cut and Remove Old Divider Plate Weld New Divider Plate The actual exposure expended for this task was approximately 62 person-rem as compared to the estimate of 29 person-rem. The following RWP controlled activities contributed significantly to this total exposure:

a. Welding of S/G divider plates (item 0 of table 3C)

Discussion The exposure expended for welding the new S/G divider plates was approximately 58 person-rem as compared to the estimate of 15 person-rem. The additional exposure is attributed to working in radiation fields higher than originally estimated and performing repairs that required more time in the higher radiation fields.

2. Task 812 - Install New Steam Generator Weld Channel Head The actual exposure expended for this task was approximately 238 person-rem as compared to the estimate of 200 person-rem. The following RWP controlled activities contributed significantly to this total exposure:

a. Weld preparation of S/G channel head remnants (item 2 of table 3C).

b. Installation and welding of new S/G lower assemblies (item 3 of table 3C).

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Discussion The exposure expended for weld preparation of the S/G channel head remnants was approximately 13 person-rem as compared to the estimate of approximately 8 person-rem. The exposure expended for the installation and welding of the new SGLAs was approximately 210 person-rem as compared to the estimate of 192 person-rem. As discussed in Progress Report No. 3, the additional exposure for these activities is attributed to working in radiation fields higher than originally estimated (i.e. original estimate was based on general area radiation fields of 5 to 20 mR/hr in the S/G channel heads; the actual radiation fields after channel head decontamination and shielding were in the range of 50 to 200 mR/hr) and erforming repairs that required more time in the higher radiation fields i.e.~ approximately 29,000 actual person-hours expended as compared to

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3.0

SUMMARY

OF DOSE REDUCTION TECHNI UES (ALARA PRINCIPLES) 3.1 General This section discusses the techniques and practices which were effective in providing exposure reduction to personnel throughout the Unit 0 SGRP.

Recommended changes in techniques and methods that should be evaluated to determine their effects on further reducing personnel exposure for steam generator replacement-channel cut method are included where applicable. A discussion of the reasons for the lower expended exposure for the Unit 0 SGRP as compared to the Unit 83 SGRP is also presented. Where available data permits, the following evaluations include a quantitative assessment of the person-rem savings attributed to the techniques used.

3.2 Tem orar Shieldin The use of temporary shielding in the Unit 0 SGRP was effective in reducing dose rates in high traffic and work areas. It is difficult to quantify the exposure savings realized from the use of temporary shielding but experience has shown that substantial reductions in exposure to personnel results from such practices.

The exposure expended for the installation and removal of temporary shielding for the Unit 3 and 0 SGRP was approximately 03 and 15 person-rem respectively.

The lower expended exposure for the Unit 0 SGRP temporary shielding activities can be attributed to the reduced amount and type of temporary shielding installed, particularly that shielding installed for components and piping inside the biological shield wall on the 10'levation of the reactor containment building. Observation of work activities performed during the Unit 3 SGRP indicated that shielding inside the biological shield wall could be minimized; therefore, piping such as RTD loop bypass lines were minimally shielded. Worker experience in installing the lead during the Unit 3 SGRP is also credited to the lower expended exposure during the Unit 0 SGRP.

Recommendations for Consideration The use of free-standing shielding supports versus direct placement of shielding should be considered as an exposure reduction technique. Free-standing shielding supports can provide the following advantages:

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a) Eliminate the need for seismic evaluation and load analysis of the component to be shielded.

b) Usually permits the use of additional shielding since loading of the component is not a factor.

c) Allows access to component behind the shield to conduct inspections such as ISI.

d) Usually results in lower exposure since this type support is normally installed in lower dose rate areas (i.e. further away from the radiation source).

e) Eliminates exposure associated with removing/installing insulation as usually required for direct placement of shielding.

3.3 General Containment Decontamination The initial and on-going containment decontamination program employed during the Unit 3 dc 0 SGRP is a practice which was recognized as extremely beneficial in reducing exposure (through effective control of contamination) thereby reducing the need for respiratory protection devices in most cases. It was also effective in reducing the volume of radioactive waste material generated.

The total exposure for initial and on-going decontamination during the Unit 3 and 0 SGRP was approximately'6 and 53 person-rem respectively. Although the benefit of decontamination activities, in terms of exposure savings, is difficult to quantify, the maintenance of good radiological working conditions is considered a successful ALARAtechnique.

3.0 Steam Generator SVater Level The exposure savings realized as a result of maintaining a high water level in the steam generator secondary side was approximately 035 and 050 person-rem during the Unit 3 and 0 SGRP respectively. A detailed listing of the activities benefiting from maintaining a high S/G secondary side water level are discussed in Radiological Progress Report f/2 for the Unit 3 and 0 SGRP.

3.5 Contamination Control Envelo es and Yentiiation The use of contamination control envelopes and ventilation were extremely effective in maintaining contamination control and preventing the spread of airborne radioactivity. Details of this practice are discussed in Radiological Progress Report /71 for the Unit 3 and 0 SGRP. The benefits observed for these techniques were:

a) The use of large contamination control envelopes, such as the enclosure around the lower steam generator assembly girth cut area, largely eliminated delays and interference with work in adjacent areas.

b) The overall potential for airborne contamination in adjacent areas and the spread of contamination was minimized.

c) Airborne contamination levels were at low concentrations as a result of using an absolute filtered ventilation system in the enclosures.

d) Supervisory personnel could observe the work in progress through viewing windows installed in the enclosure thereby minimizing exposure and the use of respiratory protection devices.

3.6 Concrete Cuttin 0 erations The use of water-cooled concrete cutting equipment was extremely effective in minimizing airborne activity. The run-off water contained a slight amount of radioactivity and was discharged as an effluent release. The total exposure expended for concrete cutting and installation during the Unit 3 and 4 SGRP was:

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Cherry picker concrete removal 32.8 30.4 and installation Concrete block removal 30'6" 12.7 8.5 and 58'levation Installation of concrete 30'6" 8.5 7.1 and 58'levations TOTAL 54.0 46.0 The use of this concrete cutting equipment allowed the removal of concrete block in large sections thereby minimizing time in the radiation area. In addition, the removal of blocks in large sections made survey assessments and decontamination of concrete surfaces relatively simple. Also, the concrete sections removed were initially painted during construction, thereby minimizing the depth of contamination into the concrete. This resulted in a reduced volume of contaminated material to be disposed of as radioactive waste.

3.7 Channel Head Decontamination and Shieldin The decontamination of the S/G channel head surfaces and use of channel head shielding during the Unit 3 and 4 SGRP were extremely effective in lowering the total exposure for SGLA installation. The exposure savings realized for the Unit 3 and 4 SGRP as a result of this decontamination and shielding were approximately 4400 and 5450 person-rem respectively.

The exposure expended for decontamination of the S/G channel heads (alumina grit-blast method) for the Unit 3 and 4 SGRP was approximately 155 and 91 person-rem respectively. The lower expended exposure for S/G channel head decontamination during the Unit 4 SGRP can be attributed to improved system reliability and arrangement. System improvements included: improved and higher pressure grit-blast pumps; improved electro-mechanical equipment (valves, controls, etc.); and improvements in mechanical spray arm attachment to minimize breakdowns. The major change in system arrangement for the Unit 4 SGRP was the location of the used grit mixing container and associated

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operating equipment outside the containment. This container was located in the Radwaste Building (adjacent to Unit 0 containment). Temporary hard piping runs were installed from the containment via the equipment hatch to the container in the Radwaste Building. This temporary piping was shielded to minimize exposure to personnel during transfer of the grit from the holding tank in containment.

During the Unit 3 SGRP, the used grit was collected in containers located in contaiment thereby contributing additional exposure to personnel in the area.

Based on the experience gained from the Unit 3 S/G channel head decontamination, changes were made in an attempt to reduce exposure to personnel involved with installation of the new SGLAs. These changes included regrogramming the computer operated spray nozzle arm to decontaminate hard to reach areas (e.g. divider plate to channel head weld) and using a grit-blast nozzle adapted for decontamination of the S/G manways. Specific details relative to S/G channel head decontamination can be found in Radiological Progress Report N2 for the Unit 3 and 0 SGRP.

S/G channel head shielding (includes nozzle shielding) was utilized during the Unit 3 and 0 SGRP. This shielding was effective in reducing exposure to personnel working in the channel heads. General area dose rates as a result of channel head and nozzle shielding were reduced from ranges of approximately 0.6 R/hr - I R/hr to levels of 0.05 R/hr 0.2 R/hr in the Unit 3 SGRP and 0.05 R/hr to 0.1 R/hr in the Unit 0 SGRP. As stated earlier, the estimated exposure savings for this technique is included with total exposure savings for channel head decontamination and shielding.

Recommendations for Consideration With regard to S/G channel head decontamination, the following recommendations are submitted:

a) Conduct visual examination of grit-blast results after necessary passes are completed to assure that all areas of interest have been adequately decontaminated. Darkened areas, particularly at hard to reach areas such as weld seams, indicate that additional grit-blast may be required. These areas can contribute to significant dose rates as localized "hot" spots.

b) Evaluate the most effective method to decontaminate the S/G manway opening to the lowest practical dose rate. The hand held grit-blast nozzle used during the Unit 0 SGRP was adequate but could be improved upon.

Dose rates in the S/G manways were typically 1 R/hr and 0.2 R/hr during the Unit 3 and 0 SGRP respectively, while dose rates in the channel head after channel head and nozzle shielding were typically .05 to .2 R/hr.

c) Evaluate use of a back-flush filter system to minimize filter changes during grit-blast operations. If a back-flush filter system is not used, then a dual set of filter banks should be used to maintain sytem operation while changing out the used set of filters.

3.8 Flame and Machine Cuttin erations The exposure expended for the S/G lower girth and divider plate cuts are as follows:

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Lower Girth Cut Divider Plate Unit S/G Method Person-rem Method Person-rem 3 A Machine 20 Flame 8.5 3 B Flame 8 Flame 5.0 3 C Flame 17 Flame 8.0 Unit 3 TOTALS 21.9 Lower Girth Cut Divider Plate Unit S/G Method Person-rem Method Person-rem A Machine 8 Flame 2.0 B Machine 7 Flame 0.3 C Machine 7.5 Flame 1.3 Unit 0 TOTALS 22.5 3.6 The lower expended exposure for the Unit 0 SGLA lower girth cuts can be attributed to improvements in the cutting machine equipment and experience gained from the Unit 3 SGRP. Additional experience was gained with both the flame and machine cutting equipment since this equipment was used to cut the channel heads from the new SGLAs to be installed.

The lower expended exposure for the Unit 0 S/G divider plate cuts is attributed to the use of remotely operated flame cutting equipment and the experience gained from using this equipment on the S/G channel heads removed from the new SGLAs.

The S/G upper girth cut was also completed using the flame cutting technique.

The exposure expended during the Unit 0 SGRP for this activity was approximately 3 person-rem.

As discussed in Unit 3 SGRP Radiological Progress Report 85, flame cutting operations require detailed preparation and control of flame temperature.

Channel head flame cutting operations during the Unit 3 SGRP resulted in additional exposure since more time was needed to complete weld preparation of the channel head remnants due to the removal of slag material. Such repairs were not required during the Unit 0 SGRP.

3.9 IVeld Pre aration of S/G Channel Head Remnants The techniques that were beneficial in minimizing exposure to personnel conducting channel head remnant weld preparation are discussed in Radiological Progress Report 82 for the Unit 3 and 0 SGRP.

The exposure expended for S/G channel head remnant weld preparation was:

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Person-rem 3 A 17 A 3.1 3 B 29 B 3 C 23 C 5.2 TOTAL 69 TOTAL 12.7

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In addition to the exposure reduction techniques previously referenced, the lower expended exposure for S/G channel head remnant weld preparation during the Unit 0 SGRP can be attributed to machining equipment improvements and to the lower radiation fields in the work area which resulted from effective grit-blast decontamination of the channel head and the use of channel head shielding.

Also, all three S/Gs were machine cut for the Unit 0 SGRP while only one S/G was machine cut for Unit 3 (the other two being flame cut). As stated earlier, machine cutting resulted in much Jess weld preparation time, since the removal of slag material deposited on the channel head remnants (caused by flame cutting) did not occur.

3.10 Installation of Steam Generator Lower Assemblies (SGLAs)

The techniques utilized during installation of the new SGLAs were discussed in Unit 0 SGRP Radiological Progress Report //2. These methods were effective in minimizing exposure and airborne activity as well as controlling the spread of contamination.

The exposure expended for the installation and welding of the new SGLAs (Task 12 of Table 2) was approximately 051 and 238 person-rem for the Unit 3 and 0 SGRP respectively. The exposure attributed to SGLA welding (371 and 188 person-rem for the Unit 3 and 0 SGRP respectively) are included in this total.

The remaining installation exposure is mainly due to preheat and post-weld heat treatment of the lower girth weld, tube cleaning, installation and removal of tube sheet protection, installation and removal of channel head and nozzle shielding and QC inspections.

In addition to the exposure reduction techniques previously referenced, the lower expended exposure for the installation of the SGLAs in the Unit 0 SGRP can be attributed to the following:

a) The revision of S/G lower girth weld procedures to minimize occupancy time in the S/G channel heads (higher radiation fields), thereby reducing the expended exposure.

b) Lower radiation fields in the S/G channel head and manways as a result of decontamination and shielding.

c) Improved tube sheet protection which minimized tube cleaning.

Approximately 20 person-rem was expended to clean and inspect tubes during the Unit 3 SGRP where approximately 8 person-rem was expended in the Unit 0 SGRP.

It should be noted that the insulation installed on the new Unit 0 S/Gs was a blanket type and not the "suitcase" type which requires detailed measured fitting. The blanket type insulation resulted in a significant exposure savings to personnel due to the significant decrease in labor hours required for installation.

The exposure expended in the Unit 3 SGRP was approximately 86 person-rem as compared to approximately 0 person-rem in the Unit 0 SGRP. The exposure expended for installation of S/G insulation is included in Task 3 of Table 2.

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10 Recommendations for Consideration The following recommendations are submitted with regard to installation of SGLAs:

a) Review SGLA weld and installation procedures to minimize occupancy time in higher radiation fields.

b) Evaluate the number of temperature indicators needed for preheat and post-weld heat treatment operations.

c) Determine the effectiveness of the tube sheet protection used to prevent smoke penetration into the tubes.

3.11 Weldin of Steam Generator Divider Plates The techniques discussed in Radiological Progress Report NO and 83, for the Unit 3 and 0 SGRP respectively, were beneficial in minimizing exposure to personnel.

A review of the exposure expended for S/G divider plate welding indicated the following:

Unit S/G Person-rem Unit S/G Person-rem 3 A 38 A 20 3 B 07 0 B 19 3 C 35 C 16 TOTAL 120 TOTAL 59 In addition to the exposure reduction techniques previously referenced, the lower expended exposure for S/G divider plate welding in the Unit 4 SGRP can be attributed to the experience gained from the Unit 3 SGRP and the lower radiation fields in the S/G channel head.

3.12 Reactor Head Pre aration for Hot Functional Testin Temporary shielding was beneficial in reducing the exposure expended for reactor head work prior to and after the hot functional testing during the Unit 3 and 0 SGRP. The activities benefiting from the use of this shielding are discussed in Radiological Progress Report 3 for Unit 0 SGRP.

The exposure expended for these activities was approximately 53 and 31 person-rem for the Unit 3 and 0 SGRP respectively. Without the benefit of reactor head shielding, the exposure expended in the Unit 3 and 0 SGRP would be in the range of 90 to 120 person-rem, thus a significant savings was realized.

3.13 Steam Generator Stora e Com ound As discussed in Radiological Progress Report N3 for the Unit 0 SGRP, the Unit 0 SGLAs were placed in the storage compound with the three Unit 3 SGLAs already in place. Surveys indicate dose rates of approximately 0.1 to 0.0 mR/hr contact with the walls and approximately 25 to 35 mR/hr contact with the roof of the storage compound. The S/G storage compound is located in the RCA and is surveyed each quarter as part of the periodic surveillance requirement.

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11 The exposure expended for transporting and storing the SGLAs in the compound was approximately 30 and 6 person-rem for the Unit 3 and 0 SGRP respectively.

The lower expended exposure (Unit 0 SGRP) can be attributed to the experience gained from the Unit 3 SGRP with regard to S/G rigging and handling and to the fact that the Unit 0 SGL'As did not have to be placed in temporary storage as in the Unit 3 SGRP.

3.10 General Techni ues and Practices In addition to the specific exposure reduction techniques described thus far, the more general techniques and methods described in the Radiological Progress Reports for the Unit 3 and 0 SGRP contributed to the adequate control of personnel exposure during both projects. Experience has demonstrated that such techniques and practices contributed significantly to an effective dose reduction (ALARA)program.

3.15 Discussion of Unit 0 SGRP Lower Ex ended Ex osure In addition to the exposure reduction techniques previously discussed, significant factors that contributed to the lower expended exposure for the Unit 0 SGRP include the following:

a) A hi her state of readiness - equipment, materials, and personnel were better prepared for the scheduled Unit 0 SGRP, thereby minimizing delays.

Such was not the case for the Unit 3 SGRP where an extended outage, for reasons other than steam generator related, resulted in the start of the Unit 3 SGRP several months ahead of schedule.

b) Retention of ex erienced ersonnel - many of the supervisors and foremen who participated in the Unit 3 SGRP were involved with the Unit 0 SGRP, thus providing the benefit of experience. Also certain contractor groups utilized during the Unit 3 SGRP were recontracted for specific work during the Unit 0 SGRP (i.e. concrete cutting, channel head cutting, channel head decontamination).

c) Greatl im roved lannin and schedulin many Unit 0 SGRP tasks were conducted in parallel and also scheduled so as to perform the work in lower radiation fields (e.g. certain. Unit 3 SGRP activities on the 58'levation were completed when general area dose rates were higher as a result of parallel defueling operations and reactor vessel inspection). Daily planning and shift turnover meetings were held to maintain job coordination, determine task status and resolve any problems, thus duplication of work and on-the-job delays were minimized. These meetings were attended by supervisors of all trade disciplines (including Health Physics).

d) Less e ui ment and i in interference - the physical arrangement of electrical equipment and piping in the Unit 0 containment is different from the Unit 3 arrangement. This difference reduced the number of interferences needed to be removed (and later reinstalled); thus a significant amount of time and exposure was saved.

e) Im roved e ui ment o eration and reliabilit equipment, including flame and machine cutting equipment, grit-blast decontamination components,

12 remote welding apparatus, etc., were significantly improved since the Unit 3 SGRP. These improvements and modifications helped to reduce the time needed to complete various tasks thus reducing the personnel exposure expended.

f) Hi h level of worker roductivit - a high degree of supervisory interaction with the labor force together with improved planning and scheduling minimized idle time in containment which resulted in less. exposure to personnel. The fact that the Unit 0 SGRP was conducted during the relative cooler months (November 1982 - April 1983) should have contributed to worker comfort, thereby improving productivity as well. A significant amount of Unit 3 SGRP activities was performed during the hotter, more humid months (June 1982 - November 1982).

g) Lower radiation fields - general area radiation levels in Unit 0 containment were typically 5-10% lower than the radiation levels experienced in the Unit 3 SGRP. In addtion, the Unit 0 S/G channel head dose rates (prior to decontamination and lower assembly removal) were approximately 25-30%

less than the dose rates observed in the Unit 3 S/G channel heads. As previously discussed, dose rates in the Unit 0 S/G channel head (after decontamination and shielding - tube sheet removed) were approximately 50% lower than the dose rates observed in the Unit 3 S/G channel heads.

As stated earlier, these factors and the exposure reduction techniques previously discussed, resulted in a significant lower expended exposure for the Unit 0 SGRP (i.e. approximately 2152 and 1305 person-rem for the Unit 3 and 0 SGRP respectively). Also, the total labor expended in radiation fields was'significantly lower for the Unit 0 SGRP (approximately 260,000 person-hours) as compared to the Unit 3 SGRP (approximately 320,000 person-hours). The lower expended exposure and total labor time for the Unit 0 SGRP clearly demonstrates the applications of the learning experience gained from the Unit 3 SGRP.

0.0 RADIOACTIVE EFFLUENTS AND SOLID SVASTE 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.

Laundry operations were the major source 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 throughout the project.

Approximately 01% 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 activitity (excluding tritium) included-the following radionuclides: Cs-137 (21%), Cs-130 (11%), Cs-136 (0.3%) and radioiodines (27%). The total activity released (excluding tritium) was approximately 10% of the total estimated activity projected to be released for the Unit 0 SGRP (refer to Table 5.2-7 of the SGRR). The amount of tritium released from Unit 0 SGRP activities was approximately 25% of the amount estimated (Table 5.2-7 of the SGRR).

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13 0.3 Airborne Releases Airborne releases for this reporting period originated primarily from continuous ventilation of the containment during post-installation phase'repair activities. A summary of airborne releases for the entire project 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 during'he Unit 0 SGRP was less than 19% of the total estimated activity projected to be released (Table 5.2-3 of the SGRR).

0.0 Solid Radioactive Waste A summary of solid low-level radioactive waste generated and shipped as a result of Unit 0 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 as a result of the Unit 0 SGRP (excluding the steam generator lower assemblies) was approximately 52% greater than the volume estimated in the Gould Affidavit dated 3une 12, 1981. It should be noted that the final 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 shipment, which are not accounted for when initially generated. The total quantity of radioactivity shipped as a result of the Unit 0 SGRP (for the volume of repair project waste generated)'was approximately 66% of the activity estimated in the SGRR.

An additional 2,000 cubic feet of low-level radioactive waste is anticipated to be generated over the next several weeks due to final cleanup. This additional waste volume is expected to be shipped off-site to a disposal facility for burial by 1 October 1983.

5.0 CONCLUSION

S AND OBSERVATIONS The following general conclusions and observations are based upon information contained in this report:

a) The total exposure expended (by SRPD) for the entire Unit 0 SGRP was well below the estimated range of 1,730 - 2,080 person-rem and considerably lower than the total exposure expended for the Unit 3 SGRP.

The total exposure expended for the Unit 0 SGRP (approximately 1305 person-rem) was 63% of the total estimated value (2080 person-rem) and 00% less than the Unit 3 total exposure of approximately 2152 person-rem.

The exposure reduction techniques described in Section 3 together with the benefit of the experience gained from the Unit 3 SGRP were contributing factors to the success of the Unit 0 SGRP. The total exposure savings directly attributed to these factors was approximately 6000 person-rem. It is important to note that the actual exposure savings is significantly higher than this value since the more general dose reduction techniques used and experience gained from the Unit 3 SGRP cannot be readily quantified.

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The actual labor expended for the Unit 0 SGRP (approximately 260,000 person-hours) was greater than the estimate of 208,000 person-hours but significantly less than the labor expended for the Unit 3 SGRP (approximately 319,000 person-hours). The total labor savings for the Unit SGRP (approximately 59,000 person-hours) results in a conservative estimated exposure savings of approximately 295 person-rem. This value is based on the Unit 0 SGRP average exposure rate per person

[i.e. total exposure expended (1305 person-rem) divided by the total labor reported (260,000 person-hours) or approximately 5 millirem per person-hour ].

b) Radioactive liquid effluents released were well within the total estimate projected to be released in Table 5.2-7 of the repair report. The calculated activity (excluding tritium) was approximately 10% while the tritium activity was approximately 25% of the total estimated activity in the SGRR.

c) Airborne releases of radioactivity attributed to repair project activities were below the estimates provided in the SGRR. The majority of the reported noble gas, particulate and radioiodine activity released occurred during the initial venting of containment which was attributed to the scheduled refueling shutdown and not the SGRP.

d) Solid low-level radioactive waste generated during the Unit 0 SGRP (excluding the SGLAs) was approximately 52% greater than the estimate provided in the Gould Affidavit dated 3une 12, 1981. The amount of compacted dry active waste generated (approximately 28,000 cubic feet) was greater than the estimate (approximately 13,000 cubic feet) indicated in Table 1 of the Gould Affidavit. This additional volume is primarily due to the conservatism employed in assigning the volume of waste. generated to the Unit 0 SGRP since some of the work was not directly related to the repair project.

e) The total quantity of radioactivity (for repair project waste shipped) was below the activity estimated in the SGRR.

The waste generated as a result of the Unit 0 SGRP was expeditiously shipped off-site, consequently, there was no significant volume of waste accumulated on-site throughout the repair project.

A small volume of low-level radioactive waste is expected to be shipped off-site after sorting the equipment and materials used during the Unit 0 SGRP. This remaining volume (approximately 2000 cubic feet) is expected to be shipped off-site to a disposal facility for burial by 1 October 1983.

The Unit 0 SGRP was completed several weeks ahead of the time scheduled for completion. This timely completion was the result of detailed job planning and coordination and effective application of experience gained from the Unit 3 SGRP.

15 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 trolley, 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.

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16 TABLE 1 (continued)

DESCRIPTION OF MAJOR 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 8. 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.

11. Cut and remove old divider 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.

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17 TABLE 2 PERSONNEL EXPOSURE

SUMMARY

- PER TASK REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 0 LABOR EXPENDED IN RADIATIONFIELD PERSONNEL EXPOSUREa li (PERSON-HOURS) (PERSON-REM)

TASK DESCRIPTION ESTIMATED ACTUAL ESTIMATED ACTUAL

1. Concrete and structural steel 13,660 22,539 88 71.09 removal and replacement.

2. Construction of pedestal 10j280 2,135 32 0.83 cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.

3. Removal, modification and 20,600 03,772 256 205.00 reinstallation of steam generator upper assemblies and major piping.

0. Construction of temporary 19,120 32,025 215 100.56 facilities and support services

5. General decontamination and 02,310 03,870 201 180.80 disposal of contaminated materials/cleanup.

6. Removal and reinstallation of 8,850 18,280 125 100.12 miscellaneous piping equipment and insulation.

7. Non-manuals (e.g. QC, 68,500 00,733 036 160.58 Engineers, Health Physics).

8. Decontamination of the 1,800 5,550 210 90.71 channel head.

9. Cut channel head and remove 3,200 0,916 166 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

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18 TABLE 2 (continued)

PERSONNEL EXPOSURE

SUMMARY

- PER TASK REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 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 3,065 29 62.10 plate, weld new divider plate.

12. Install new steam generator 11,000 36,886 200 237.61 weld channel head.

13 Placement of steam generator 225 200 , 6.10 in storage.

TOTAL . 207,595 260,023 2,080 1,300.82 Estimated Range 1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.

TABLE 3A

SUMMARY

OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 31 HARCll 1983 TO 16 HAY 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-COHPLETE)

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

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

2. Reactor Cavity Decontamination. 162 0.00 0.00 1.51

3. Reactor Cavity Liner Plate Inspection. 0 300 0.00 0.00 6.04

4. Install S/G Transfer Bridge. 960 147 1.21 0.00 0.29

5. Remove Emergency Containment Coolers. 140 78 1.68 0.00 0.24

6. Remove CRDM Coolers and Fans. 67 215 0.28 0.00 1.34 C

7. Rerate Polar Crane and Load Test. 4,571 1,481 9.49 0.00 2.97

8. Disassemble Manipulator Crane and Store. 128 0.00 0.00 0.91

9. Install Cherry Pickers. 2,430 266 6.06 0.00 1.35

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

TABLE 3A (Continued)

SUMMARY

OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING 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 PROCRESS)

11. Disconnect/Remove Permanent Electrical Equipment and Cables. 430 304 1.93 0.00 0.79

12. Install Temporary Pouer, Lighting and Electrical Items. 1,148 4,458 49.50 0.00 18.55

13. Remove Miscellaneous Steel. 580 3,532 6.21 0.00 8.20

14. Install/Maintain S/0 Temporary Containments and Ventilation. 1,008 l>013 17.63 0.00 . 2.92

15. Install Temporary Shielding. 120 I I 193 2.38 0.00 11.27

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

17. Cut and remove concrete 30' and 58'levation. 5,334 4,173 52.30 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 31 HARCH 1983 TO 16 MAY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIHATED FOR REPORTINC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COHPLETE)

(PERSON-HOURS) (PERSON-BOURS) (PERSON-REH) (PERSON-REM) (PERSON-REM) (I-IN PROCRESS)

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

21. Remove/dispose of contaminated materials, 900 3)009 7.41 0.00 18.64

22. Crane operation/maintenance. 685 3,722 1.36 0.00 7.63

23. Miscellaneous Activities. 1,000 71560 l. 51 0.00 11.21 Total - PHase I 34,992 49,422 .283 0.00 229.99

TABLE 3B SUHHARY OP REHOVAL ACTIVITY EXPOSURES REPORTING PERIOD 31 MARCH 1983 TO 16 HAY 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-110URS) (PERSON-REH) (PERSON-REM) (PERSON-REH) (I LN PROGRESS)

1. Remove insulation from A, B, & C S/0's. 3,500 6,721 77.00 0.00 63.64

2. Remove feedyyater piping A, B, & C S/C's. 147 2>932 1.50 0.00 10.76

3. Remove main steam piping A, B, & C S/C's. 125 331 0.61 0.00 1.76

4. Remove miscellaneous piping from Ay By & 0 S/0 cubicles ~ 1,410 1,370 17.62 0.00 18.11 C

5. Conduct channel head decontamination Ay By & C S/C's. 1,835 5,547 214.00 0.00 90.71 6, Cut A, B, & C S/C upper assemblies. 630 683 33.30 0.00 2.88 I

7. Lift A, B, & C S/C upper assemblies, invert and place in racks. 525 1,575 6.75 0.00 7.74

8. Cut A, B, & C S/0 channel heads. 714 2,115 60.24 0.00 22.33

9. Install tube bundle shield covers A, B, & C S/C's. 525 916 53.00 0.00 14.82

TABLE 3B (Continued)

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTIHC PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTIHC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

10. Cut A,.B & C S/C divider plates. 252 317 3.36 0.00 3.64

11. Lift A, B & C SCLA, cut and remove seismic rings. 1,089 221 77.16 0.00 3.59

12. Install tube sheet shield covers A, B & C S/C's. 755 1,124 40.00 0.00 16.39

13. Remove A, B & C SCLA's from reactor containment building and place in storage compound. 225 200 25.00 0.00 6.14 C

14. Maintain temporary power, lighting & electrical items. 2, 100 2,793 55.00 0.00 5.93

15. Maintain, erect, and remove scaffolding. 840 7,308 8.40 0.00 31.47

16. On going decontamination activities. IO>900 2,540 32.76 0.00 12.74

17. Remove/dispose of contaminated materials. 3,600 7,617 29.62 0.00 37.65

TABLE 3B (Continued)

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTIHG PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT UHIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTIOH LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

18. Project non~anual support. 27>725 6,410 214.72 0.00 24.58 I

19. Containment tool and weld rod room support. 840 39 2.52 0.00 0.09

20. Crane operation and maintenance. 3,015 2,334 5.44 0.00 4.05

21. Miscellaneous Activities. 8,377 1,364 58.00 0.00 16.60 Total - Phase .II 69,129 54,457 1,016 0.00. 395.62

TABLE 3C SUHHARY OF INSTALLATION ACTIVITY EXPOSURES REPORTINC PERIOD 31 MARCH 1983 TO 16 HAY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDFD ESTIMATED FOR REPORTINC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

1. Remove S/C upper assembly internals and install/modify A, B and C S/C secondary internal components. 11,260 6,286 93.10 0.00 14.01

2. Weld preparation of A, B & C S/C channel head remnants. 840 1,757 7.71 0.00 12.69

3. Install/veld A, B & C SCLA's (includes post-weld heat treatment). 8,696 27,143 191.64 0.00 213.77

4. Install/veld A, B & C S/C

'ivider plates. 1,554 2,760 15.10 0.00 58.46 C-

5. Install/veld A, B & C S/C upper'assemblies. 6,280 8,432 23.82 0.00 13.60

6. Installation of A, B & C S/C main steam piping. 1,250 996 5.50 0.00 2.28

7. Installation of A, B & C S/C feedvater piping. 1,680 1,013 6 ~ 80 0.00 1.89

8. Install insulation A, B & C S/C's, 3,486 2>435 29.40 0.00 4.17

9. Maintain temporary pover, lighting and electrical items. 2,850 7,819 65'.00 0.00 19.14

TABLE 3C (Continued)

SUMMARY

OF IHSTALLATIOH ACTIVITY EXPOSURES REPORTIHG PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPEHDED STATUS ACTIVITY DESCRIPTIOH LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

10. Maintain/erect/remove scaffolding. 2,840 17>625 20.67 0.00 58.58

11. On-going decontamination activities. 10,920 32.76 0.00 14.41

12. Remove/dispose of contaminated materials. 31600 141931 29.62 0.00 54.16

13. Project non-manual support, 14,460 25,448 86.27 0.00 74.37

14. Containment Tool 6 Weld'od room support. 840 458 2.52 0.00 0.84

15. Crane operation/maintenance. 2,740 5,296 5.43 0.00 4.11

16. Miscellaneous activities, 8,704 5,044 28.66 0.00 16.12 Total Phase III 82,000 132,539 644 0.00 562.60

TABLE 30

SUMMARY

OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTINC PERIOD 31 MARCN 1983 TO 16 MAY 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO"DATE (C-COMPLETE)

(PERSON-NOURS) (PERSON-)10URS) (PERSON-REM) (PERSON-REM) (PERSON"REM) (I-IN PROGRESS)

1. Remove temporary containments 970 1,129 5.97 0.00 4.10 C and ventilation.

2. Installation of miscellaneous 600 3 j348 2.33 2.23 9.61 steel.

3. Installation of miscellaneous 350 3,817 7.58 0.00 12.3?

piping in S/C cubicles.

4., Installation of permanent 580 5.00 1.13 2.72 electrical cables/equipment.

5. Installation of concrete stop logs, 5,490 2,539 22.08 0.00 7.10 concrete forms, rebar and pouring of neu concrete 30'6" & 58'l.

6. Installation of emergency 210 1,122 2.52 0.01 2.25 containment coolers.

7. Installation of CRDM coolers 100 64 0.42 0.00 0.28 and fans.

8. Install manipulator crane. 484 1.14 1.63

TABLE 3D (Continued)

SUMHARY OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 31 MARCH 1983 TO 16 HAY 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-REH) (PERSON-REH) (PERSON-REM) (I-IN PROGRESS)

9. Installation of reactor coolant 0 1>227 0 0.00 4.68 C pump motors.

10. S/G tube cleaning and inspection. 302 0.00 8.31

11. Conduct S/C secondary hydrostatic 281 0.00 0.59 testing.

12. Reactor preparation/hot 850 30.42 30.94 functional testing.

13. Removal of secondary exhaust 140 252 3.03 0.0i 1.75 C ~

system.

14. Remove temporary shielding. 84 532 2.10 4.12

15. Remove scaffolding all 830 672 7.85 1.81 1.81 C elevations.

16. On-going, decontamination 2, '730 370 8 '0 1.56 1.56 activities.

17. Rcmove/dispose of 900 3>190 7.41 11 '0 11.50 contaminated materials.

18. Project non-manual support, 1,720 1,534 24.75 6.69 6.69

TABLE 3D (Continued)

SUMMARY

OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTINC PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY 19.

20.

ACTIVITY DESCRIPTIOH Containment tool and weld rod room support.

Crane operation and maintenance.

ESTIMATED LABOR (PERSON"HOURS) 210 685 LABOR EXPENDED TO DATE (PERSON-HOURS) 89 160 ESTIMATED EXPOSURE (PERSON-REM) 0.63 1.36 FOR REPORTIHG PERIOD (PERSON-REM)

0. 14

0. 14 EXPENDED TO-DATE (PERSON-REM) 0.14 0.14 STATUS (C-COMPLETE)

(I-IH PROCRESS) t

21. Miscellaneous. 5,875 . 1>497 39.77 3.90 4.32 Total Phase IV 21,474 24,005 141 60.78 116.61

TABLE 4 PERSONNEL EXPOSURE

SUMMARY

PER PHASE REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UHIT 4 TOTAL ESTIMATED ACTUAL EXPOSURE PHASE STATUS PHASE ESTIMATED LABOR ACTUAL LABOR ESTIMATED EXPOSURE FOR REPORTIHC ACTUAL EXPOSURE (C-COMPLETE)

DESCRIPTIOH EXPENDED TO-DATE EXPEHDED TO-DATE EXPOSURE EXPENDED TO-DATE PERIOD EXPENDED TO-DATE (I-IN PROGRESS)

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

Preparation 34,992 49,422 283 283 0. 00 229.99 Re>>>oval 69>129 54,457 1,016 1,016 0.00 395.62 Installation 82,000 132>539 644 644 0.00 562.60 Miscellaneousa 21,474 24,005 141 141 60.78 116.61 Project totals 207>595 260,423 2,084 2,084 60.78 1,304.82 aMiscellaneous (post-installation) - includes cleanup, storage and c>iscellaneous preparations prior to start-up.

TABLE 5

SUMMARY

OF RADIOACTIVE EFFLUENT RELEASES REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 1983 I. LIQUID EFFLUENT RADIOACTIVITY RELEASED IH LIQUID EFFLUENTS t

RELEASES (CURIES)

TOTAL ACTIVITY TOTAL RELEASED THIS RELEASED DURING APRIL MAY REPORTIHG S/C REPAIR RADIONUCLIDE 3/31 4/27 4/28 - 5/16 PERIOD TO DATE Ag-110m 2.888-04 2.88E-04 5.97E-04 Co"58 5.478-04 8.268-05 6.30E-04 1.278-02 Co-60 1.53E-03 2.32E-04 1.768-03 1.85E-02 Cs-134 3.468-04 4.358-05 3.90E-04 8.758-03 Cs-136 1.90E-04 Cs-137 7.02E-04 8.368-05 7.868-04 1.638-02 I-131 1.79E-02 I-133 2.50E-03 I-135 2.608-04 Mn-54 4.47E-05 3.20E-06 4.79E-05 2.42E-04 Nb-95 8.538-05 TOTAL 3.46E-03 4.458-04 3 '08-03 7.80E-02 Tritium Released (Curies) 0.0 0.0 0.0 4.7E+01 VOLUME RELEASED VOLUME RELEASED Liquid Effluent Volume THIS REPORTINC DURING S/C REPAIR Released (Liters) PERIOD TO DATE 9.38E+05 3.40E+05 1.28E+06 9.79E+06 Hot etectab e

V TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVE EFFLUEHT RELEASES REPORTIHC PERIOD 31 MARCH 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 1983 I. AIRBORNE RADIOACTIVITY RELEASED IN AIRBORNE EFFLUENTS RELEASES (CURIES)

TOTAL ACTIVITY TOTAL A. NOBLE CASES RELEASED THIS RELEASED DURIHC APRIL MAY REPORTINC S/C REPAIR RADIOHUCLIDE 3/31 - 4/27 4/28 5/16 PERIOD TO DATE Ar-41 3.528-01 Kr-85 4.09E-01 Kr-85m 2.23E-01 Kr-88 1.39E-01 Xe-131m 1.37E+00 Xe-133 8.62E+02 Xe-133m 3.89E+00 Xe-135 6.59E+00 TOTAL 8.75E+02 TRITIUM 2.65E-02 B. HALOCENS Br-82 1.90E-04 I-131 3.308-02 I-133 5.628-03 TOTAL .88E-02

• Hot Detectable

TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVE EFFLUENT RELEASES REPORTING PERIOD 31 MARCll 1983 TO 16 MAY 1983 TURKEY POINT - UNIT 4 1983 I. AIRBORNE RADIOACTIVITY RELEASED IN AIRBORNE EFFLUENTS RELEASES (CURIES)

TOTAL ACTIVITY TOTAL C. PARTICULATES RELEASED TllIS RELEASED DURING APRIL MAY REPORTIHG S/C REPAIR RADIONUCLIDE 3/21 4/27 4/28 5/16 PERIOD TO DATE Ba-140 2.00E-05 Co-57 3.50E-07 Co-58 1.10E"05 3.608-06 1.46E-05 3.79E-04 Co-60 2.40E-05 1.20E-05 3.60E-05 2.82E"04 Cr-51 1.20E-05 Cs-134 4.00E-06 1.808-06 5.808-06 1.13E-04 Cs-136 3.548-05 Cs-137 1.10E-05 4.708-06 1.578-05 2 '2E-04 I-131 1.04b-04 La-140 1.40E-05 Mn-54 3.70E-06 7.908-07 4.498-06 2.50E-05 Hb-93 3.10E-06 Ru-103 3.80E-06 TOTAL 5.37E-05 2.298-05 7.66E-05 1.22E-03

• Not Detectable

TABLE 6

SUMMARY

OF SOLID LOW-LEVEL RADIOACTIVE WASTE REPORTING PERIOD 31 MARCH 1983 TO 16 MAY 1983

'URKEY 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 5,250 27,992.

Non-Compacted Dry Active Waste 500 3,700

'Resin and Filter Media 100 1)590 Channel Head Decontamination Waste 595 Miscellaneous Totals 5,850 33,881 II. SOLID LOW-LEVEL REPAIR ACTIVITYWASTE SHIPPED REPORTING PERIOD VOLUME LLWa SHIPPED ESTIMATED ACTIVITYb 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 3 February 83 - 30 March 83 8,591 7.058 31'March 83- 16 May 83 5,016 05.239 Totals 29)015 173.279 LLW Low-level (radioactive) waste.

Predominant radionuclides 37Cs, Co, 58Co.