ML17341B018

Steam Generator Repair Program,Radiological Progress Rept, 811231-820302.

ML17341B018
Person / Time
Site:	Turkey Point
Issue date:	04/05/1982
From:	FLORIDA POWER & LIGHT CO.
To:
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ML17341B017	List: ML17341B016 ML17341B018
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NUDOCS 8204120220
Download: ML17341B018 (51)

Text

STEAM GENERATOR REPAIR PROGRAM FOR TURKEY POINT UNIT 3 RADIOLOGICAL PROGRESS REPORT - NO. 0 FOR THE PERIOD DECEMBER 31, 1981 THROUGH MARCH 3, 1982 DOCKET NO. 50-250 LICENSE NO. DPR-31 FLORIDA POWER AND LIGHT COMPANY

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TABLE OF CONTENTS PAGE NO.

1.0 INTRODUCTION

2.0 OCCU PATIONAL RADIATION EXPOSU RE 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) 0 3.1 General 3.2 Contamination Control Envelopes and Ventilation 3.3 Welding of Steam Generator Divider Plates 3.0 Reactor Head Preparation for Hot Functional Testing 3.5 General Techniques and. Practices 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General 0.2 Liquid Releases 0.3 Airborne Releases 0.0 Solid Radioactive Waste

5.0 CONCLUSION

S AND OBSERVATIONS TABLES TABLE 1 Description of Major Tasks 9 TABLE 2 Personnel Exposure Summary - Per Task 11 TABLE 3A Summary of Preparatory Activity Exposures 13 TABLE 3B Summary of Removal Activity Exposures 15 TABLE 3C Summary of Installation Activity Exposures 17 TABLE 3D Summary of Post-Installation A'ctivity Exposures 19 TABLE 0 Personnel Exposure Summary - Per Phase 21 TABLE 5 Summary of Radioactive Effluent Releases 22 TABLE 6 Summary of Solid Low Level Radioactive Waste Shipments 25

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1.0 INTRODUCTION

Radiological Progress Report No. 0 contains information pertaining to the radiological aspects of the Unit 3 Steam Generator Repair Program (SGRP) for the period December 31 through March 3. This. information includes the following:

a. An assessment and summary of the occupational exposure and labor expended for each reporting period (throughout the project).

b. An evaluation of the effectiveness of dose reduction techniques (ALARA principles).

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

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

Significant project. tasks performed during this reporting, period included:

.1. Inspection and close-out of steam generators in preparation for testing.

2. Installation of miscellaneous steel.

3. Installation of reactor coolant pump motors.

0. Installation of emergency containment coolers, control rod drive mechanism, coolers and fans.

5. Installation of insulation on steam generators.

6. Reactor preparation for hot functional testing.

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

8. Welding of S/G divider plates.

9. Installation of miscellaneous piping in S/G cubicles.

Several on-going activities also performed during this period included: maintenance of temporary scaffolding, cleanup and decontamination,-maintenance of temporary electrical power and lighting services, health physics support and project supervision.

2.0 OCCUPATIONAL RADIATION EXPOSURE 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 is discussed in detail in Section 2.1 - 2.3 of Radiological Progress Report No. I. This program was utilized throughout this reporting period. A description of the thirteen'(13) major tasks is indicated in Table l.

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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 through this reporting period (i.e., from project commencement on 20 June 1981 to 3 March, 1982).+ Also included are the original estimated expenditures. The following comments are provided for clarification and should be considered when reviewing the data presented in Table 2.

a. Several activities performed during the repair effort which were not described in Table 1 have been appropriately placed into one of the major task categories in Table 2 and accordingly accounted for.

b. Exposures received by certain pre-identified personnel (e.g., health. physics, QC/QA, etc.) performing functions not directly attributable to any one task are listed separately in Item 7.

c. Information detailing exposures reported for specific activities within a major task is contained in the data base. This information is utilized to "track" exposure for the time period of interest.

A detailed summary of the personnel exposure expended through this reporting period for preparatory, removal, installation and post-installation activities are 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. The following comments are provided for clarification and should be considered when reviewing the data presented in Tables 3A, 3B, 3C, 3D 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.

co For completed activities it should be noted that small amounts of additional exposure and labor may appear sometime after completion is indicated, as a result of such factors as: field changes to procedures, work involving activity related to support equipment, localized work area cleanup, etc.

+Self-reading pocket dosimeter (SRPD) results are used to report person-rem since exposure information is immediately available upon exit from,the RCA and accordingly recorded in the computer data base. Since thermoluminescent dosimeters (TLD's) are processed primarily on a monthly basis this information could not be readily incorporated into the exposure expended for each specific activity.

Historically, SRPD results are higher than TLD results primarily due to drift (caused by factors such as heat and humidity, and initial charging). Therefore, the accumulated dose reported may be considered as conservative.

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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 98% of the original total estimate. These exposures are recorded by computer acquisition as discussed in Progress Report No. 1. Table 2 includes all exposure expended through March 3, 1982 and will continue to be used for accumulation of all personnel exposures through project completion. The exposure expended to date for activities performed during the preparatory, removal, installation and post-installation phases is summarized in tables 3A, 3B, 3C and 3D respectively.

As discussed in Progress Report No. 3, tables 3A and 3B show that the total actual exposure expended for preparatory and removal phase activities was approximatley 00% less than the total estimated exposure for those activities.

Table 3C shows that the total occupational exposure accumulated for installation phase activities was approximately 865 person-rem as compared.to the original exposure estimate of 600 person-rem. The exposure attributed'to steam generator lower assembly installation (approximately 051 person-rem) was significantly higher than the estimate of 190 person-rem (items 2 and 3 of table 3C). The exposure attributed to welding the steam generator divider plates (approximately 120 person-rem) was also significantly higher than the estimate of 15 person-rem (item 6 of table 3C).

Table 3D shows that the total occupational exposure accumulated for post-installation phase activities in progress is approximately 375 person-rem as compared to the original exposure estimate of 101 person-rem.

Table 3D indicates that several post-installation activities resulted in significant exposure above the estimated exposure for those. activities. These activities included:

1. Installation of miscellaneous piping and steel (items 2 and 0)

2. Removal of scaffolding and contaminated materials (items 10 and 11).,

3. Miscellaneous activities - Q.C. inspections, project supervision, etc.

(item 10).

The above activities resulted in an. expended exposure of approximately 277 person-rem as compared to the total estimate of 95 person-rem for those activities. Table 3D also indicates that a few activities resulted in significant exposure that were not included in the original estimate. These activities included:

1. Installation of reactor coolant pump motors (item 5).

2. Reactor preparation for hot functional testing (item 12).

3. S/G tube cleaning/inspection A, B dc C S/G's (item '13).

These activities resulted in an expended exposure of approximately 66 person-rem.

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The information for all phase activities in progress or completed (as detailed in Tables 3A, 3B, 3C and 3D) is summarized in Table 0. The total exposure expended during this reporting period was approximately 592 person-rem.

3.0 APPLICATION OF DOSE REDUCTION TECHNI UES (ALARA PRINCIPLES) 3.1 General'his section discusses the techniques and practices which have been effective in providing dose reductions to personnel during the reporting period. Where available data permits, the following evaluations include a quantitative assessment of the person-rem savings which can be attributed to the techniques used.

3.2 Contamination Control Envelo es and Ventilation Enclosures for contamination control and a filtered ventilation system were utilized during installation of the steam generator divider plates. Welding and divider plate preparation operations resulted in low-level airborne radioactivity which was effectively controlled with the filtered ventilation system. At times, during divider plate installation, it was necessary to install the filtered exhaust ductwork in the channel head with the work crews to assure adequate ventilation

,in the work area. Contamination control enclosures were modified as needed to

,maximize channel head accessibility. These modifications assured positive personnel access control as well as controlling the spread of relatively higher levels of contamination to surrounding areas.

3.3 Weldin of Steam Generator Divider Plates Exposure reduction techniques similar to those techniques utilized for steam generator channel head remnant weld preparation and steam generator lower assembly (SGLA)'installation (discussed in previous reports) were employed during welding of the steam generator divider plates. These techniques included:

a) Controlling access/egress to S/G work platforms from outside the biological shield wall where dose rates are typically ten times less than dose rates inside the shield wall.

b) Using contamination enclosures on the.work platforms to minimize airborne radioactivity and the spread of contamination to adjacent areas.

c) Utilizing filtered ventilation ducting to exhaust low level airborne radioactivity from the work area.

d) Utilizing channel head shielding whenever practical'to reduce exposure rates during divider plate welding and repair operations.

The exposure expended for installation of the steam generator divider plates was approximately 120 person-rem. Dose rates in the channel head without any shielding were approximately 1,000 mR/hr. With channel head shielding installed, area dose rates were on the order of 200-000 mR/hr. Without the benefit of channel head shielding, the exposure expended would be approximately 000 person-rem. Thus, a conservative savings of approximately 280 person-rem was realized.

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The exposure expended for all SGLA installation activities was approximately 600 person-rem. Without the benefit of head shielding and decontamination of the S/G channel heads, the exposure expended would have been approximately 5,000 person-rem. Thus a conservative exposure savings of approximately 0,000 person-rem was realized. A discussion of exposure expended for SGLA installation activities is discussed in sections 3.6, 3.0 and 3.3 of Radiological Progress Reports No.'s 2, 3 and 0 respectively.

3.0 Reactor Head Pre aration for Hot Functional Testin Lead shielding was installed on the reactor head to reduce exposure rates for those activities performed to prepare for hot functional testing and removal of the reactor head after hot functional testing. The following activities will have the benefit of reactor head shielding:

l. Installation and removal of instrument port conoseals.

2. Detensioning and tensioning of the reactor head.

3. Installation and removal of reactor head studs.

The exposure expended to date for the above activities is approximately 30 person-rem. Without the benefit of head'shielding, the exposure expended would have been approximately 60 person-rem. An update on the exposure savings

,realized. as a result of reactor head shielding will be discussed in a future report since all activities. associated with the hot functional testing were not completed during this report period.

3.5 General Techni ues and Practices II In addition to the assessment of dose reduction techniques described above, it is important to note some of the more general techniques and practices employed to maintain adequate control of personnel radiation exposure. These practices include the following:

a) A comprehensive health physics program which includes an extensive training and radiological. surveillance program.

b) Use of repair project process sheets.

c) Utilization of "in-containment" low-level radiation waiting areas.

d) Use of portable area radiation monitors to provide workers on the spot continuous exposure rate information.

e) Ongoing decontamination and periodic work clean-up program.

f) Use of continuous air samplers in addition to periodic grab samples.

g) Use of in-containment tool cribs and weld rod rooms. A detailed description of these techniques and practices are discussed in Progress Report No. l.

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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 and located in the vicinity of each S/G enclosure to allow direct communication. with the Health Physics Shift Supervisor. This system enables the!health physics technician to maintain continuous communication with the shift supervisor thereby minimizing delays (and.person-rem expended) on the job.

j) Multi-badging for evaluation of personnel exposure for those tasks performed in relatively complex radiation fields.

k) Use of temporary lead shielding in high occupancy/traffic areas.

Experience has shown that the practices and techniques. discussed in this section have contributed significantly to an effective overall dose reduction (ALARA) program for the repair project.

0.0 RADIOACTIVE EFFLVENTS AND SOLID V/ASTE 0.1 General Radioactive effluents, compromised 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 continue to be the major source of liquid releases for the

.Unit 3 repair project . As shown in Table 5 the composition of radioactive

'isotopes detected remain, relatively unchanged from those detected during the previous period. Approximately 80% of the total activity released to date was in the form of relatively long-lived corrosion products. The remaining 20% was in

,the. form of fission products (which include Cs-130 and Cs-137) and activation products. The total activity released to date is approximately 21% of the total estimated activity to be released during the repair project on Unit 3.

0.3 Airborne Releases Airborne releases for this reporting period originated primarily from continuous ventilation of the containment during repair activities. A summary of airborne releases is shown in Table 5 as well. As indicated in previous progress reports the particulates detected were typical of radionuclides expected as a result of an extended shutdown. The total activity released through this reporting period is.

less than 1%(a) of the total estimated activity projected to be released.

0.0 Solid Radioactive 'Waste A summary of solid low-level radioactive waste generated and shipped to date as a result of Unit 3 steam generator repair activities is provided in Table 6. The low-level waste shipments during this reporting period. were made to both the (a) This value was incorrectly reported in Radiological Progress Report No. 3 as 26%. The correct value should have been 1%.

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5.0 CONCLUSION

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

a) The actual exposure expended for installation phase activities is approximately 865 person-rem as compared to the. original estimate of 600 person-rem. Approximately 65% (570 person-rem) of the. actual exposure expended for the installation phase was attributed to. steam generator channel head interior weld repairs, lower assembly. installation activities and welding of S/G divider plates. The estimated exposure for these activities was approximately 200 person-rem. As discussed in Radiological Progress Report No.3, this higher expended exposure is attributed to personnel working in radiation fields higher than originally estimated and performing repairs that required more time in the higher radiation fields.

The actual exposure expended for post-installation phase activities through this reporting period is approximately 375 person-rem as compared to the estimate of 101 person-rem. As discussed in. section 2.3 of this report,

.several post-installation activities resulted in the actual exposure exceeding that estimated for the activity or significant exposure accumulated for an activity that was not included in the original estimate.

For those post-installation activities estimated, the increased exposure can be attributed to the fact that more time was required in radiation fields to complete the work than originally estimated. The exposure expended for post-installation activities not included in the original estimate are a result of uncertainties in predicting the entire scope of work for the repair project - channel head cut method.

Table 0 shows that the actual labor expended to date for the installation and post-installation phase (approximately 128,000 person-hours and 82,000 person-hours respectively) is considerably higher than the estimated labor for those phases (approximately 82,000 person-hours and 21,000 person-hours respectively). Table 0 also indicates that the actual labor (approximately 303,000 person-hours) expended for the entire project to date is significantly greater than the entire project estimate of approximately 208,000 person-hours. The significant increase in actual person-hours expended versus estimated person-hours demonstrate the uncertainties in predicting the total labor expenditure for the repair project. A discussion of the uncertainties in, predicting labor expenditures for the repair project is included in section 3.3.7.2 of the Steam Generator Repair Report (SGRR).

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V/ith the repair project nearing completion, the total exposure projected for the entire project has been re-estimated at 2,200 person-rem. This value is well within the range predicted for the repair project (i.e.'between 1730 and 2080 person-rem).

b) Radioactive liquid effluents continue to remain within the total release estimate presented in Table 5.2-7 of the repair report. The calculated activity is less than 21% of the estimated total activity in the Steam Generator Repair Report (SGRR).

c) Airborne releases of radioactivity remain below the estimate indicated in the SGRR. No radioiodine or gaseous activity was detected. Airborne activity discharged throughout the Unit 3 repair project is not expected to exceed the estimate indicated in the SGRR.

d) Solid low-level radioactive waste generated to date (excluding the steam generator lower assemblies) is approximately 28%'greater than the estimate provided in the Gould Affidavit dated June 12, 1981. The total quantity of radioactivity for repair project waste shipped to date remains significantly below the activity estimated in the SGRR.

Progress Report Number 5 will contain information from March 0, 1982 through project completion (early April, 1982). This final report will also contain a summary for those tasks where the actual person-rem expended is significantly greater than the estimated. values. This summary will include a discussion for the higher expended exposure and the additional ALARAtechniques planned for utilization in the Unit 0 SGRP as a.result of the experience gained from the Unit 3 SGRP.

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9 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 2. This task includes installation/removal of preparation. of the pedestal crane foundations, assembly pedestal'ranes,,

polar crane, miscellaneous and erection of cranes and the. polar crane cribbing. platforms, S/G trolley, and disassembly and removal of transf er bridge. cranes and the polar crane trolley.

3. Removal, modif ication 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 1V and 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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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, 70 The non-manual category includes health Engineers, HPs). physi'cs, 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 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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11 TABLE 2 PERSONNEL EXPOSURE

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PER TASK REPORTING PERIOD 20 JUNE 1981 TO 3 MARCH 1982 H

TURKEY POINT - UNIT 3 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSURE>

TASK DESCRIPTION (PERSON HOURS) 'PERSON-REM)

ESTIMATED ACTUAL ESTIMATED ACTUAL

1. Concrete and structural steel 13,660 21,767 88 86.76 removal and replacement.

2. Construction of pedestal 10,280 10,020 32 31.60 cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.

3. Removal, modification and 20,600 71,820 256 289.71 reinstallation of steam generator upper assemblies and major piping.

0. Construction of temporary 19,120 18,925 215 96.29 facilities and support services

5. General decontamination and 02,310 23,165 201 165.96 disposal of contaminated materials/cleanup.

6. Removal and reinstallation of 8,850 39,850 125 181.68 miscellaneous piping -equipment and insulation.

7. Non-manuals (e.g. QC, 68,500 50,500 036 270.29 Engineers, Health Physics).

8. Decontamination of the 1,800 6,503 210 155.12 channel head.

9. Cut channel head and remove 3,200 9,710 166 109.70 old steam generator lower assembly.

10. Weld shield cover on lower assembly:

a. at channel head 760 526 00 10.10

b. at transition end 530 978 53 16.09

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PERSONNEL EXPOSURE

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REPORTING PERIOD 20 3UNE 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSURE>

(PERSON HOURS) (PERSON-REM)

TASK DESCRIPTION ESTIMATED ACTUAL ESTIMATED ACTUAL 1'1. Cut and remove old divider 2,600 6,079 29 101.86 plate, weld new divider plate.

12. Install new steam. generator 11,000 39,011 200 050.82 weld channel head.

13 Placement of steam generator 225 25 30.18 in storage.

331'03,197 TOTAL 207,595 2,080 2,000.60 Estimated Range 1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.

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TABLE 3A SENARY OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 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-REH) (I-IN PROGRESS

l. Initial Containment Decontamination 6,020 2,108 45.00 0.00 27.07

2. Reactor Cavity Decontamination and 373 0.00 5.58 Inspection

3. Install Steam Generator Transfer 960 1,473 1.21 0.00 7.80 Bridge

4. Remove Emergency Containment 6J860 5,157 11.83 0.00 7.80 Coolers, Control Rod Drive Mechanism Coolers and Fans, Manipulator Crane, and Rerate Polar Crane and Load Test

5. Install Cherry Pickers 2,430 2,990 7.15 0.00 17.88

6. Remove Reactor Coolant Pump 386 0.00 2.43 Motors 7; Disconnect/

Electrical Remove Permanent Equipment and Cables 430 281 3.31 0.00 2,50 c ~

8. Install Temporary PoverJ 1, 148 2,962 49.48 0.00 11.68 Lighting and Electrical Cables

9. Remove Miscellaneous Steel 580 1,702 1.25 0.00 7.05

10. Install Temporary Containments 245 1, 740 4.29 0.00 12.62 and/or Ventilation Systems

TABLE 3A (Continued)

SUGARY OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT UNIT 3 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 PROGRESS)

11. Install Temporary Shielding 120 1,388 2.58 0.00 31.05

12. Install Scaffolding All Levels 1,440 1,895 13.27 0.00 9.95

13. Cut and Remove Concrete 5,334 3,913 58.00 0.00 45.49

14. Miscellaneous Activities 9J425 5,419 85.63 0.00 59.04 TOTAL - PHASE I 34,992 31,787 283.00 0.00 247.94

TABLE 3B SLDQIARY OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTLNG 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 PROGRE

1. Remove insulation from A, B & C 3,850 7,669 77.00 0.00 70.80 steam generator

2. Remove Feedwater Piping A, B & C 147 1.50 0.00 9.95 steam generator 2,473'3,379

3. Cut A, B & C S/G Upper Assembly 6,318 126.40 0.00 60.02 (U.A.) and remove and modify U.A. internals

4. Install tube bundle shield covers 530 978 53.00 0.00 16.49 A, B & C S/G

5. Cut divider plate & channel head 1,722 5,087 97 '4 0.00 72.07 A, B & C S/G - Rig to 58'levation

6. Rig/lift A, B & C S/G Lower Assembly 84 142 6.60 0.00 0.72 (L.A.) to cut/remove seismic ring

7. Install tube sheet shield cover 760 527 40.00 0.00 10.10 Ag B & C S/G

8. Lift A, B & C S/G U.A., invert and 525 2,143 6.75 0.00 11.79 C place in rack 9~ Remove main steam piping A, B & C 126 499 0.61 -

0.00 2.84 S/G

10. Install laydown cribbing for A, B & C 252 199 2.65 0.00 0.49 S/G 58'levation

0 TABLE 3B (Continued)

SUKc1ARY OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 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 PROGRESS

11. Conduct channel head decontamination 1,840 6,503 214.00 0.00 155.12 A1 B & C S/G

12. Remove miscellaneous piping from 1,410 6,050 17.62 0.00 29.79 C A, B & C S/G cubicles

13. 'Remove A. B & C S/G L.A. from RCB 225 322 25.00 0.00 30.18 and transfer to storage compound

14. Maintain temporary power lighting 2,100 1,578 55.00 0.00 4.70 and electrical cables

15. Maintain/erect/remove scaffolding 840 5,686 8.40 0.00 29.85

16. Ongoing decon activities/remove and 14,500 2,914 62.40 0.00 16.57 dispose contaminated materials

17. Miscellaneous TOTAL PHASE II Activities 33,900 69,129 5, 103 611252 221.93 1016.00 0.00 0.00 31.00 552.48 c

~

TABLE 3C S190fARY OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 31 .DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT UNIT 3 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 PROGRES.

1. Installation of A> B & C S/G 17 ) 540 6,534 73.70 0.12 9.81 C Upper Assemblies 2.* Weld Preparation of A, B & C 840 4,552 7.71 0.00 69'09 S/G Channel Head Remnants

3. Installation and Welding of 8,360 35,359 182.00 11.13 381.74 A, B & C S/G Lower Assemblies

4. Installation of A, B & C S/G 1,250 2,065 5.50 3.47 4.16 Main Steam Piping

5. Installation of A, B & C S/G 1,680 4,884 6.80 8.68 15.71 Feedwater Piping

6. Welding of A, B & C S/G 1,554 5,478 15. 10 118.57 119.86 Divider Plates

7. Install Insulation Steam Generators A, B & C 3s486 18,427 29.40 52.05 52.05 c

~

8. Maintain Temporary Power, 2,850 6,301 65.00 0;00 13.99 Lighting and Electrical Cables

9. Maintain/Erect/Remove Scaffolding 21840 9,794 21.80 0.00 31.81

10. Ongoing Decon Activities/ 14,500 12~280 62.40 25.18 66.19 Remove/Dispose Contaminated Materials

0 TABLE 3C (Continued)

SUMMARY

OP INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED POR 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 PROGRESS) 11 'iscellaneous Activities 27~190 22,699 "

174.59 34.24 100.60 C TOTAL PHASE III 82,000 128,373 644.00 253.44 865.01

TABLE 3D

SUMMARY

OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 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 PROGRESS

1. Installation of concrete stop logs, 5,490 3, 190 22.00 4.11 7.36 concrete forms, rebec and pouring of new concrete 30'6" and 58'levation

2. Installation of miscellaneous 350 11,100 8.00 31.05 52.35 piping in S/G cubicles

3. Installation of emergency 310 57 3.00 0.22 0.22 containment coolers, control rod drive mechanism cooler and fans

4. Installation of miscellaneous 600 12,962 2.00 26.20 26.87 steel

5. Installation of A, B 6 C reactor 864 0.00 3.17 3.17 coolant pump motors

6. of steam generator 7.

Removal transfer bridge Installation of permanent electrical 500 663 1.00 0.00 1.19 c

~

580 2,020 6.00 7.51 7.51 cables, equipment.

8. Removal of temporary containments 970 2,707 12.00 5.17 5.17 and ventilation systems

9. Removal of temporary shielding 84 782 2.00 11 ~ 12 11.12 I

TABLE 3D (Continued)

SUMMARY

OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT UNIT 3 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-RRi) (I-IN PROGRES

10. Removal of scaffolding all levels 830 9,537 8.00 35.17 35.17

11. Ongoing decon activities/removal/ 3,630 11~242 15.00 60.68 60.68 disposal contaminated materials

12. Reactor preparation/hot functional 952 0.00 38.89 38.89 testing

13. Tube cleaning/inspection A, B & C 1,283 0.00 23.83 23.83 S/Gs

14. Miscellaneous Activities 87130 24,426 62.00 91.28 101.64 PHASE ACTIVITY TOTALS 21)474 81,785 141.00 338.40 375.17 TOTAL PHASE IV 7,704 20,646 48'00 78.67 104.41 (Completed Tasks Only)

~5 0 TABLE 4 PERSONNEL EXPOSURE

SUMMARY

PER PHASE REPORTING 'PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 TOTAL ESTIMATED ACTUAL EXPOSURE PHASE STATUS PHASE ESTIMATED LABOR ACTUAL LABOR ESTIMATED EXPOSURE FOR REPORTING ACTUAL EXPOSURE (C"COMPLETE)

DESCRIPTION EXPENDED TO-DATE EXPENDED 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 Removal 34,992 31,787 283 283 0.00 247.94 . ~

69,129 61,252 1,016 1,016 0.00 552.48 Installation 82,000 128,373 644 644 253.44 865.01 Miscellaneousa 21,474 81,785 141 141 338.40 375.17 Project totals 207,595 303,197 2,084 2,084 591.84 2,040.60. NA (Completed Phases Only) 186,121 221,412 1,943 1,943 N/A 1,665.43 NA aMiscellaneous (post-installation) - includes cleanup, storage and miscellaneous preparations prior to start-up.

"NA - not applicable at this time.

TABLE 5

SUMMARY

OF RADIOACTIVE EFFLUENT RELEASES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 1982 I. LIQUID EFFLUENT RADIOACTIVITYRELEASED IN LIQUID EFFLUENTS RELEASES (CURIES)

TOTAL 'ACTIVITY TOTAL RELEASED THIS RELEASED DURING JANUARY FEBRUARY 5/G REPAI~

ISOTOPE 12/31-2/3 2/4-3/3 REPORTING PERIOD TO DATE ~

Co-57 9.30E-05 3.20E-05 1.25E-04 1.33E-04 Co-58 2.32E-02 5.96E-03 2.92E-02 5.06E-02 Co-60 1.98E-02 8.74E-03 2.85E-02 3.93E-02 Cs-134 1.40E-05 1.40E-05 1.85E-03 Cs-137 2.36E-04 1.14E-04 3.50E-04 3.6IE-03 Fe-59 4.33E-04 Mn-54 1.20E-03 1.79E-04 1.38E-03 2.14E-03 Zn-65 1-131 Nb-95 3.50E-04, Sb-124 2.40E-04 2.15E-03 2.39E-03 3.93E-03 Sb-125 6.68E-04 3.49E-03 4.16E-03 7.72E-03 W Ag-110m 2.13E-03 3.08E-04 2.44E-03 3.08E-03 .

Zr-95 3.68E-04 3.68E-04 8.33E-04 TOTAL 4.79E-02 2.10E-02 6.89E-02 1.14E-OI .

VOLUME RELEASED VOLUME RELEASED Liquid Effluent Volume THIS REPORTING DURING S/G REPAIR Released (Liters) 1.39E+06 6.90E+05 PERIOD TO DATE 2.08E+06 9.2IE+06

+Not detectable

TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVEEFFLUENT RELEASES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 1982 I. AIRBORNE RADIOACTIVITYRELEASED IN AIRBORNE EFFLUENTS RELEASES (CU RIES)

TOTAL ACTIVITY TOTAL A. NOBLE GASES RELEASED THIS RELEASED DURING 3ANUARY FEBRUARY REPORTING S/G REPAIR~

ISOTOPE 12/31-2/3 2/0-3/3 PERIOD TO DATE Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 TOTAL B. HALOGENS 1-131 1-133 TOTAL

+Not Detectable

4 0

TABLE 5 (Continued)

SUMMARY

OF RADIOACTIVE EFFLUENT RELEASES REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 1982 I. AIRBORNE RADIOACTIVITYRELEASED IN AIRBORNE EFFLUENTS RELEASES (CURIES)

TOTAL ACTIVITY TOTAL C. PARTICULATES RELEASED THIS RELEASED DURING ISOTOPE 3ANUARY 12/31-2/3 FEBRUARY 2/4-3/3 REPORTING PERIOD S/G REPAI~

TO DATE ~

Ce-141 Ce-144 Co-58 1.2E-07 8.0E-08 2.00E-07 2.34E-05 Co-60 S.IE-06 3.7E-06 1.18E-05 1.79E-04 Cs-134 3.3E-OS 3.30E-OS 1.87E-06 Cs-1'37 3.7E-07 1.8E-07 5.50E-07 8.38E-'06 Fe-59 Mn-54 2.6E-OS 2,60E-08 7,63E-07 Zn-65 Nb-95 1.15E-07 TOTAL 8.62E-06 3.99E-06 1.26E-05 2.14E-04

+Not Detectable

i5

~ 'y

)+

p 25 TABLE 6

SUMMARY

OF SOLID LOW-LEVEL RADIOACTIVEWASTE REPORTING PERIOD 31 DECEMBER 1981 TO 3 MARCH 1982 TURKEY POINT - UNIT 3 I. SOLID LOW-LEVEL RADIOACTIVEWASTE GENERATED FROM U-3 S/G REPAIR WASTE FORM VOLUME'LLWaIN CU-'FT VOLUME'LLWIN CU-FT FOR REPORTING PERIOD TO DATE Compacted Dry Active Waste 7,980 18,585 Non-Compacted Dry Active Waste 825 0,855 Resin and Filter Media 595 1,615 Channel Head Decontamination Waste 717.5 Miscellaneous 2/775 Totals 9,000 28,507.5 II. SOLID LOW-LEVEL REPAIR ACTIVITYWASTE SHIPPED REPORTING PERIOD VOLUME LLWa SHIPPED ESTIMATED ACTIVITY>

DAT.ES IN CU-FT CU RIES 20 3une 81 - 22 August 81 3,905 1.08 23 August 81 -3 November 81 6,700 22.62 0 November 81 - 30 December 81 6,030 5.03 31 December 81 -3 March 82 9,050 10.00 Totals 26,525 39.53 a LLW Low-level (radioactive) waste.

b Predominant isotopes 137Cs, 60Co, 58Co.

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