ML17341B224

Final Radiological Progress Rept(5),810624-820407.

ML17341B224
Person / Time
Site:	Turkey Point
Issue date:	06/04/1982
From:	FLORIDA POWER & LIGHT CO.
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ML17341B223	List: ML17341B222 ML17341B224
References
NUDOCS 8206140159
Download: ML17341B224 (66)

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~ P STEAM GENER ATOR R EPAIR PROGR AM FOR TURKEY POINT UNIT 3 FINAL RADIOLOGICALPROGRESS REPORT (NO. 5)

FOR THE PERIOD 3UNE 20, 1981 THROUGH APRIL 7, 1982 DOCKET NO. 50-250 LICENSE NO. DPR-31 FLORIDA POV/ER AND LIGHT COMPANY py SaOb0450 8P061401~05000g pgR gDOCK pDR 8

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TABLE OF CONTENTS PAGE NO.

1.0 INTRODUCTION

2.0 OCCUPATIONAL RADIATION EXPOSURE 2.1 General 2.2 Description.and Format of Exposure Data 2.3 Discussion of Exposure Results 2.0 Summary of Major Tasks with Significant Expended Exposure 2.5 General Discussion of Work Activities Resulting in Underestimated Accumulated Exposure 3.0

SUMMARY

OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES) 3.1 General 3.2. Temporary Shielding 3.3 General Containment Decontamination 7 3A Steam Generator Water Level 8 3.5 Contamination Control Envelopes and Ventilation 3.6 Concrete Cutting Operations 3.7 Channel Head Decontamination and Shielding 3.8 Flame and Machine Cutting Operations 9 3.9 Weld Preparation of S/G Channel Head Remnants 9 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 General Techniques and Practices 10 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 11 0.1 General ll 0.2 Liquid Releases ll 0.3 Airborne Releases ll 0.0 Solid Radioactive Waste 11

5.0 CONCLUSION

S AND OBSERVATIONS 12

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TABLE OF CONTENTS PAGE NO.

TABLES TABLE 1 Description of Major Tasks 10 TABLE,2 Personnel Exposure 'Summary Per Task 16 TABLE 3A Summary of Preparatory Activity Exposures 18 TABLE 3B Summary of Removal Activity Exposures 20 TABLE 3C Summary of Installation Activity Exposures 22 TABLE 3D Summary of Post-Installation 'Activity Exposures 20 TABLE 0 Personnel Exposure Summary Per Phase 26 TA'BLE 5 Summary of Radioactive Effluent Releases 27 TABLE 6 Summary of Solid Low Level Radioactive IVaste Shipments 30

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1.0 INTRODUCTION

Radiological Progress Report No. 5 contains information pertaining to the radiological aspects of the Unit 3 Steam Generator Repair Program (SGRP) from project commencement 20 June 1981 through project completion 7 April 1982. 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.

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

f. A discussion of additional ALARAtechniques planned for utilization during the Unit 0 SGRP.

Significant project tasks performe'd during the final reporting period (0 March, 1982 through 7 April, 1982) included:

1. Installation of miscellaneous steel.

2. Installation of insulation on steam generators.

3. Hot functional testing

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

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 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 20 3une 1981 to project completion 7 April 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 acco'rdingly 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 expendit'ures. 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 recorded for all major tasks throughout the entire project was well within 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 00% 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'rift (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 900 person-rem as compared to the original exposure estimate of 600 person-rem. As discussed in previous progress reports, steam generator channel head interior weld repairs and lower assembly installation activities required more time in the higher radiation fields than originally estimated thereby significantly increasing the total exposure for this phase. Table 3C shows that these activities (items 2, 3 and 6 of table 3C) resulted in a total exposure of approximately 572 person-rem as compared to the original total estimate (for these activities) of 205 person-rem.

Table 3D shows that the total occupational exposure accumulated for post-installation activities was approximately 052 person-rem as compared to the original total estimate of 101 person-rem. As discussed in Radiological Progress Report No. 0, several activities resulted in significant exposure above that estimated for those activities. These activities (items 2, 0, 5, 10-10) resulted in a total expended exposure of approximately 017 person-rem as compared to the original estimate of 95 person-rem. Some of these activities (items 5, 12, 13 of table 3D) were not included in the original estimate. These activities resulted in an exposure of approximately 80 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'(0 March 1982 through 7 April 1982) was approximately 111 person-rem. As stated, the total exposure expended for the Unit 3 SGRP was approximately 2152 person-rem (by SRPD).

2.0 Summar of i%la or Tasks with Si nificant Ex ended 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 (RSVP controlled) within a major task.

1. Task N1 - Concrete and Structural Steel Removal and Re lacement The actual exposure expended for this task was approximately 97 person-rem as compared to the estimate of 88 person-rem. The following RWP controlled activities contributed significantly to this exposure:

a. Removal/replacement of miscellaneous steel (item 9 and item 0 of tables 3A and 3D respectively).

Discussion The exposure expended for the removal and replacement of miscellaneous steel was approximately 03 person-rem as compared to the estimate of approximately 3 person-rem. This higher expended exposure is attributed to performing work that required more time than originally estimated. The actual labor expended for this activity was approximately 16,000 person-hours as compared to the estimated labor of approximately 12,000 person-hours. Some of this work was performed in higher radiation fields than expected due to the reactor being refueled.

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2. Task 83 - Removal Modification and Re-installation of Steam Generator V er Asemblies and Ma or Pi in The actual exposure expended for this task was approximately 300 person-rem as compared to the estimate of 256 person-rem. The following RWP controlled activities contributed significantly to the total exposure:

a. Installation/removal of scaffolding (items 12, 15, 9, and 10 of tables 3A, 3B, 3C and 3D respectively).

b. Lifting, inverting, and placing S/G upper assemblies in racks (item 8 of table 3B).

c. Removal/replacement of piping and valves from S/G cubicles (items 12 and 2 of tables 3B and 3D respectively).

Discussion The exposure expended for the installation and removal of scaffolding was approximately 120 person-rem as compared to the estimate of approximately 51 person-rem. The additional exposure was attributed to the additional time required in the radiation field.to replace the original scaffolding installed at the start of the project with fire-retardant scaffolding. This fire-retardant scaffolding was not available at the time approval was obtained to commence the Unit 83 SGRP. Also, scaffolding activities required more time for installation and removal than was originally estimated.

The exposure expended for lifting, inverting, and placing the S/G upper assemblies in the racks was approximately 12 person-rem as compared to the estimate of 7 person-rem. The exposure expended for the removal and replacement of piping and valves from the S/G cubicles was 80 person-rem as compared to the estimate of approximately 26 person-rem. The higher exposures expended for these activities was attributed to the work requiring more time to complete than originally estimated due to changes in work scope (i.e., replacement of reactor coolant pump oil collection system and the removal and replacement of additional piping interferences not accounted for in the original estimate).

3. Task $36 - Removal and Re-installation of Miscellaneous Pi in E ui ment and Insulation The actual exposure expended for this task was approximately 216 person-rem as compared to the estimate of 125 person-rem. The following RWP controlled activities contributed significantly to this total exposure:

a. Replacement of S/G insulation (item 7 of table 3C).

b. Removal and replacement of feedwater piping (item 2 and 5 of tables 3B and 3C respectively).

c. Removal and replacement of reactor coolant pump motors (item 6 and 5 of tables 3A and 3D respectively).

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Discussion Th'e exposure expended for the replacement of S/G insulation was approximately 86 person-rem as compared to the estimate of approximately 29 person-rem. This additional exposure was attributed to the additional time required in radiation fields to install the new reflective mirror insulation. This insulation required in-place measurement and fitting. As shown in item 7 of table 3C, the labor expended to complete the task was approximately 25,000 person-hours as compared to the estimate of, approximately 3,500 person-hours.

The exposure expended for the removal and replacement of feedwater piping was approximately 26,person-rem as compared to the estimate of 8.3 person-rem. This additional exposure is attributed to the work requiring more time to complete than originally estimated.

The exposure expended for the removal and replacement of reactor coolant pump motors was. 5.6 person-rem. This activity was not included in the original scope of work; therefore, no estimate was made.

Task 4/ll Cut and Remove Old Divider Plate Weld New Divider Plate The actual exposure expended for this task was approximately 102 peison-rem as compared to the estimate of 29 person-rem. The following RWP controlled activities contributed significantly to this total exposure:

a. Plasma-arc (flame) cutting of S/G divider plate (item 5 of table 3B).

b. Welding of S/G divider plate (item 6 of table 3C).

Discussion The exposure expended for cutting the S/G divider plates was approximately 22 person-rem as compared to the estimate of approximately 10 person-rem. The exposure expended for welding the new S/G divider plates was approximately 120 person-rem as compared to the estimate of 29 person-rem. The additional exposure for these activities (as

'discussed in Progress Report /k0) is attributed to working in radiation fields higher than originally estimated and performing repairs that required more time in these higher radiation fields. Some of these repairs included the removal of a section of the S/G divider plate to allow access to the entire channel head weld area. The removal and welding, of this section was not included in the original scope of the repair work, hence no exposure or labor estimate was available.

5. Task 812- Install New Steam Generator Weld Channel Head The actual exposure expended for this task was approximately 051 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).

Discussion The exposure expended for weld preparation of the S/G channel head remnants was approximately 69 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, 383 person-rem as compared to the estimate of 182 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 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 performing repairs that required more time in the higher radiation fields (i.e. approximately 00,000 actual person-hours expended as compared to the estimate of 9,200 person-hours).

6. Task $/13 Placement of Steam Generator in Stora e The exposure expended for this task was approximately 30 person-rem as compared to the estimate of 25 person-rem. The following RV/F controlled activities contributed significantly to this total exposure:

a. Transfer SGLAs from Reactor Containment Building (RCB) to storage compound (item 13 of table 3B).

Discussion As discussed in Progress Report N2, approval was obtained to place the SGLAs in temporary storage until the storage compound was completed.

The exposure expended to remove the SGLAs from the RCB, place them in temporary storage and fill the secondary side with distilled water was approximately 18 person-rem. The exposure expended to drain the SGLA secondary side, move the SGLAs into the storage compound and weld the temporary secondary side vent and drain fittings was approximately 12 person-rem. The additional exposure for this task is attributed to placing the steam generators in temporary storage rather than directly moving them into the storage compound.

2.5 General Discussion of hVork Activities Resultin in Underestimated Accumulated

~Ex osure Two specific areas of work resulted in significant exposure above their estimated values. These areas were work on the S/G bowl during the installation phase (specifically items 2, 3 and 6 of tables 3C) and the reinstallation and removal of piping, equipment and insulation and ongoing decontamination activities (in preparation for startup) during the miscellaneous phase (specifically items 2, 0, 7, 10 dc 11 of table 3D)..

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Based on the ratio of person-rem accumulated to person-hours worked (in the radiation field) on the S/G bowl, the average radiation levels were approximately 1.2 times higher than estimated (units of person-rem per person-hour worked).

The actual labor hours worked were approximately 0.2 times greater than that estimated (excess of approximately 35,000 person-hours), resulting in an accumulated exposure underestimate of approximately 367 person-rem. As discussed in Section 3.10 and 3.11, techniques are being planned for the Unit 0 SGRP to minimize the labor hours required to complete this activity as well as reduce the radiation fields occupied.

An evaluation of the person-rem per person-hour worked for the specific miscellaneous phase activities stated above indicated that the actual average radiation fields occupied were less than that estimated but the actual'labor hours were approximately nine times greater than estimated (excess of approximately 07,000 person-hours). This resulted in an accumulated exposure underestimate of 185 person-rem. Clearly, the original estimate of labor hours required. to perform these specific activities was low. Extra efforts are being planned for the Unit 0 SGRP to minimize non-productive time in containment and minimize work in the radiation field that could be performed outside of the contain'ment building.

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SUMMARY

OF DOSE REDUCTION TECHNI UES (AL'ARA PRINCIPLES) 3.1 General This section discusses the techniques and practices which were effective in providing exposure reductions to personnel throughout the Unit 3 SGRP. Specific details describing the techniques utilized were presented in Radiological Progress Reports 1-0. )Vhere available data permits, the following evaluations include -a quantitative assessment of the person-rem savings attributed to the techniques used. Exposure reduction techniques to be utilized during the Unit 0 SGRP are currently being planned taking into account the experience gained during the Unit 3 SGRP. This includes a detailed review of all activities performed (including the re-evaluation of those activities where the actual accumulated person-rem was less than that estimated). Since a complete discussion of this planning is too voluminous to present in this report, a general discussion of the additional ALARA techniques planned for the Unit 0 SGRP are presented.

3.2 Tem orar Shieldin The use.of temporary shielding in the Unit 3 SGRP was effective in reducing dose rates in high traffic and work areas. The exposure expended for the installation and removal of temporary shielding was approximately 06 person-rem. It is difficult to quantify the exposure savings realized from the use of temporary shielding but experience has shown that substantial reductions in dose to personnel are realized from such practices.

3.3 General Containment Decontamination The initial containment and on-going decontamination program employed in the Unit 3 SGR P is a practice which is recognized as extremely beneficial in reducing exposure through effective control of contamination thereby reducing

ih the potential for airborne activity and eliminating the need for respiratory protection devices. This program is planned for utilization in the Unit 0 SGRP.

It is also effective in reducing the volume of radioactive waste material that is generated.

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 person-rem (as indicated in Progress Report P/2). It is expected that a similar exposure savings will be realized in the Unit 0 SGRP.

3.5 Contamination Control Envelo es and Ventilation The use of contamination control envelopes and ventilation were extremely effective in maintaining contamination control and minimizing the spread of airborne activity to adjacent areas. A discussion of these practices is detailed in Progress Report P/I.

3.6 Concrete Cuttin 0 erations The use of water-cooled concrete cutting equipment was extremely effective in preventing airborne activity. The run-off water contained a slight amount of radioactivity and was discharged as a plant effluent release. A discussion of concrete cutting operations were presented in Progress Reports f/I and 2.

3.7 Channel, Head Decontamination and Shieldin The exposure savings realized as a result of channel head shielding and decontamination was approximately 0000 person-rem. The activities benefiting from the S/G channel head decontamination and shieldings are detailed in Progress Reports 2, 3 and 0.

Several modifications to the S/G decontamination system are planned for the Unit 0 SGRP. These include:

a. A back-flush system for the filters to minimize filter changes.

b. Improved pump design.

c. Improved valves and operating equipment.

d. Reprogramming the existing computer operated spray nozzle arm to allow decontamination of relatively hard to reach areas((i.e., divider plate and channel bowl weld area).

e. Use of a spray nozzle adapted for the decontamination of the S/G manway openings.

f. Overall changes to enhance system reliability.

The contractor indicated that these modifications should reduce the exposure expended for channel head decontamination in Unit 0 by, 20%. This should result in an expended exposure of approximately 120 person-rem for S/G channel head decontamination during the Unit 0 SGRP.

3.8 Flame and Machine Cuttin 0 erations The use of flame and machine cutting equipment was effective in making the SGLA lower girth and divider plate cuts. As discussed in Progress Report //2, "A" S/G was machine cut while "8" and "C" S/Gs were flame cut. A review of the exposure expended for each S/G lower girth cut indicates the following:

S/G T e Lower Girth Cut Ex osure ( erson-rem)

II AI I Machine 17 Flame 29 I IC II Flame 23 Although the exposure expended for the machine cut was less, the time to complete the machine cut was six days versus one day for the flame cut. Repair project personnel are evaluating the cutting techniques to be used in the Unit 0 SGR P.

3.9 Weld Pre aration of S/G Channel Head Remnants The techniques discussed for this activity were presented in Progress Report N2 and were beneficial in minimizing exposure to personnel conducting channel head remnant weld preparation. A review of the exposure expended for this activity indicated the following:

S/G Ex osure ( erson-rem)

II AlI 123 115 IIC II 138 The machine cutting technique (as performed on "A" S/G lower girth) did not result in significantly lower exposure for channel head welding activities than the flame cutting technique, except in the case of "C" S/G lower girth cut. The flame cutting of "C" S/G resulted in additional repairs of the S/G channel head remnant which required more time in the higher radiation fields as a result of some difficulty encountered with the equipment during the cutting process.

Flame cutting equipment requires detailed preparation and control of the proper flame temperature. Repair project personnel are evaluating the flame and machine cutting techniques as planned for the Unit 0 SGRP.

3.10 Installation of Steam Generator Lower Assemblies (SLCAs)

The techniques used for the installation of the new SGLAs (discussed in Progress Report 7/3) were effective in minimizing exposure, controlling the spread of" contamination and minimizing airborne activity.

10 As discussed in 2.0, the exposure expended'for SGLA installation was significant.

Project personnel are evaluating and revising the weld preparation and applicable procedures for Unit )$ 0 SGLA installation to minimize the occupancy time required for repairs in the S/G channel head (thereby reducing the expended exposure). Also, approximately 20 person-rem (item 13 of table 3D) was expended to clean and inspect Unit 3 steam generator tubes as a result of smoke from welding activities penetrating the tube sheet protection and entering the steam generator tubes. The steam generator tube sheet protection (to be used for the Unit 0 SGRP) is being evaluated to determine.a method to prevent smoke penetration into the tubes thereby minimizing the exposure associated with tube cleaning.

3.11 Weldin of Steam Generator Divider Plates The techniques discussed in Progress Report 80 as applied to personnel welding the new S/G divider plates were beneficial in minimizing exposure. A review of the exposure expended for S/G divider plate welding indicated the following:

S/G Ex osure ( erson-rem)

II AI I 37.70 06.92 35.20 119.86 Project personnel are reviewing the techniques for divider plate cutting and welding as planned for the Unit 0 SGRP.

3.12 Reactor Head Pre aration for Hot Functional Testin The use of temporary lead shielding on the reactor head was beneficial in reducing the exposure expended for-the following activities:

1. 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 for these activities was approximately 53 person-rem.

without the benefit of head. shielding, the exposure expended would have been approximately 95 person-rem. It is expected that this technique will result in a similar exposure savings during the Unit 0 SGRP.

3.13 General Techni ues and Practices The general techniques and practices described in Radiological Progress Reports 1-0 contributed to the adequate control of personnel exposure during the Unit 3 SGRP. Experience has shown that such techniques and practices contribute

0 0 11 significantly to an effective overall dose reduction (ALARA)program. Also, numerous photographs were taken of various activities in progress throughout the Unit 3 SGRP. These photographs will be utilized to familiarize personnel with the radiological aspects of the SGRP.

0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 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 were 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 throughout the project.

Approximately 80% of the total activity released during the project 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 was approximately.21% of the total estimated activity to be released for the Unit 3 SGRP.

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 the Unit 3 SGRP was less than 1% 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 as a result of Unit 3 steam generator repair activities is provided in Table 6. The low-level waste shipments during this reporting period were made to both the Barnwell, South Carolina and Richland, Washington Low-Level Waste Disposal Facilities.

The total volume of solid low-level radioactive waste generated as a result of the Unit 3 SGRP (excluding the steam generator lower assemblies) was approximately 31% greater than the volume estimated in the Gould Affidavit dated 3une 12, 19SI. 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 3 SGRP (for the volume of repair project waste generated) was approximately 16% of the activity estimated in the SGRR. Approximately 2,260 cubic feet of radioactive waste generated during the Unit 3 project remains to be shipped off-site. This remaining volume has been scheduled for shipment to a disposal facility for burial by 30 3une, 1982.

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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 total exposure reported (by SRPD) for the entire Unit 3 SGRP was well within the estimated range of 1,730 2,080 person-rem. Experience has shown that TLD results (official exposure) are typically less than 95% of SRPD results. Thus, the official dose accumulated is less than the estimate of 2,080 person-rem.

The exposure expended for the preparatory and removal phase activities was approximately 208 and 552 person-rem respectively as compared to their respective estimates of 283 and 1,016 person-rem. The exposure reduction techniques and methods utilized in these phases are expected to result in a similar exposure savings during the Unit 0 SGRP.

The exposure expended for installation phase activities (approximately 900 person-rem) as compared to the estimate of 604 person-rem was primarily attributed to personnel working in radiation fields higher than originally estimated and performing repairs that required more time in these higher radiation fields.

The exposure expended for post-installation phase activities was approximately.052 person-rem as compared to the estimate of 101 perqon-rem. This increased exposure is primarily attributed to work requiring more time in these radiation fields than was originally estimated.

Several activities in the preparatory, installation and post-installation pha'ses were not included in the original exposure estimate. These activities included: reactor cavity decontamination and inspection (item 2 of table 3A); removal and replacement of reactor coolant pump motors (item 6 and 5 of tables 3A and 3D respectively); reactor preparation for hot functional testing (item 12 of table 3D); and tube cleaning and inspection of the steam generators (item 13 of table 3D). The total exposure expended for these activities was approximately 88 person-rem. This indicates that the total exposure (for those activities with estimates) for the project was approximately 2,060 person-rem as compared to the estimate of 2,080 person-rem.

The actual labor expended for the project (approximately 319,000 person-hours) was greater than the estimate of approximately 208,000 person-hours. This indicates the uncertainties in predicting the entire scope of work and labor expenditure for the repair project-channel head cut method.

It is expected (from the knowledge and experience gained during the Unit 3 SGRP) that the total exposure (by SRPD) for the Unit 0 SGRP will be in the range of 10 to 15% lower than, the exposure expended for the Unit 3 SGRP.

b) The dose reduction techniques (ALARA principles) utilized during the Unit 7/3 SGRP were effective in controlling personnel exposure. The total exposure savings directly attributed to these techniques was approximately 5,000 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 and methods can not be readily quantified. It is expected that a similar exposure savings will be realized during the Unit 0 SGRP.

0 0 13 c) Radioactive liquid effluents were well below the activity estimated for release in the Steam Generator Repair Report (SGRR). The total activity to be released for the Unit 0 SGRP is expected to approximate the total activity released during the Unit 3 SGRP.

d) Airborne releases of radioactivity were significantly less than the estimate indicated in the SGRR. Airborne releases for the Unit 0 SGRP are not expected to exceed the. estimate in the SGRR.

e) Solid low-level radioactive waste generated during the Unit 3 SGRP (excluding the steam generator lower assemblies) was approximately 31%

greater than the estimate provided'in the Gould Affidavit dated 3une 12, 1981. The amount of compacted dry active waste generated (approximately 21,000 cu.ft.) was greater than the estimate (approximately 13,000 cu.ft.) indicated in,table I of the Gould Affadivit. This additional volume is primarily due to the conservatism employed in assigning the volume of waste generated to the Unit 83 SGRP even though some of the work was not directly related to'the repair project.

The following waste reduction techniques were employed during the Unit N3 SGRP:: initial and ongoing decontamination program; and waste segregation and control of materials used in contaminated areas.

Compaction operations were beneficial in reducing the number of packages to be shipped for disposal. These waste reduction and compaction techniques are planned for the Unit 0 SGRP.

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

The waste generated as a result of the Unit 83 SGRP was expeditiously shipped off-site; consequently, there was no significant volume of waste accumulated on-site throughout the repair project.

The Unit 3 SGRP was completed within one week of the time scheduled for completion. This demonstrates the effectiveness of the detailed planning, coordination and job execution required for such a project. Similar planning, coordination and job execution should assure the timely completion of the Unit 0 SGRP and result in a significantly lower expended exposure.

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TABL'E 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 Erection of scaffolding to remove items'nclude:

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 20 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 mater ials/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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15 TABLE 1 (continued)

DESCRIPTION OF MA3OR TASKS TASK TASK DESCRIPTION

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

7.. Non-manuals (e.g., QC, 70 The non-manual category includes health Engineers, HPs). physics, quality control, and engineering p'ersonnel, visitors, and Bechtel personnel required for the entire outage.

S. 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. )Veld 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.

ih 45 I

16 TABLE 2 PERSONNEL EXPOSURE

SUMMARY

-~PER TASK REPORTING PERIOD 20 3VNE 1981 TO 7 APRIL 1982 TURKEY POINT - UNIT 3 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSURE>

(PERSON HOURS)'PERSON-REM)

TASK DESCRIPTION ESTIMATED ACTUAL ESTIMATED ACTUAL

1. Concrete and structural steel 13,660 23,011 88 97.11 removal and, replacement.

2. Construction of pedestal 10,280 10,029 32 31.60 cranes,. preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.

3. Removal, modification and 20,600 70,106 256 300.35 reinstallation of steam generator upper assemblies and major piping.

0. Construction of temporary 19,120 20,093 215 116.90 facilities and support services

5. General decontamination and 02,310 20,900 201 178.69 disposal of contaminated materials/cleanup.

6. Removal and reinstallation of 8,850 06,858 125 215.52 miscellaneous piping equipment and insulation.

I 7; Non-manuals (e.g. QC, 68,500 56)871 036 292.53 Engineers, Health Physics).

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

9. Cut channel head and remove 3,200 9,752 166 110.56 old steam generator lower assembly.

10. IVeld shield cover on lower assembly:

a. at channel head 760 526 00 10.10

b. at transition"end 530 978 53 16.09

0 17 TABLE 2 (continued)

PERSONNEL EXPOSURE

SUMMARY

- PER TASK REPORTING PERIOD 20,3VNE 1981 TO 7 APRIL 1982 TURKEY POINT UNIT 3 LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSURE>

(PERSON HOURS) (PERSON-REM)

TASK DESCRIPTION ESTIMATED ACTUAL ESTIMATED ACTUAL

11. Cut and remove old divider 2,600 6,080 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 225 331 25 30.18 in storage.

TOTAL 207,595 319,093 2,080 2,151.83 Estimated Range 1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.

lh i~ ~,

TABLE 3A SU",~fARY OF PRE?A'GTORY AC IVITY EXPOSURES REPORTING PERIOD 4 <<fARCH 1982 TO 7 APRIL 1982 TURKEY POINT - UNIT 3 ACTUAL ACTUAL EXPOSUPZ ACTUA'XPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTI)fATED FOR R""?ORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COi!?LETE)

(PERSON-HOURS) (PERSON-ifOURS) (PERSON-REN) (VERSO--RE~<<) (PERSON-REM) (I-IN PROGRESS)

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

2. Reactor Cavity Decontdmination and '73 0 0.00 5.58 Inspection

3. Insta)1 Steam Generator TransEer 960 ~ 1>473 1.21 0.00 7.80 Bridge Remove Emergency Containm nt 6,860 5,157 11.83 '.00 7.80 Coolers, Control Rod Drive

'mechanism Coolers and Fans,

fanipulator 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 0 386 0,00 2 ~ 43

Ãotors

7. Disconnect/ Remove Perm-nent 430 281 3.31 0.00 2.50 Electrical Equipment and Cables

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

9. Rer ove Hiscelianeous Steel 580 1)702 1,25 0.00 7.05

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

'0 TABLE 3A (Continued) ~ ~

SU>MARY OF PREPARATORY ACTIVPTY EXPOSURES REPORTING PERIOD 4 KCRCH 1982 TO 7 APRIL 1982 TURKEY POINT UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTBATED 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)

11. Install Temporary Shielding 120 11388 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 9,425 5,419 85.63 0.00 59.04 TOTAL PHASE I 34,992 31,787 283.00 0.00 247.94

0 0 I

TABLE 3B SFDfARY OF RENOVAL ACTIVITY EXPOSURES REPORTING PERIOD 4 >RRCH 1982 TO 7 APRIL 1982 TURKEY. POINT - UNIT 3-ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTiVITY ESTIMATED LABOR EXPENDED ESTIiLKTED FOR REPORTING EXPEND"D S A'US ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO"DATE (C-COHPLETE)

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

1. Remove insulation from A, B & C 3)850 7,569 77.00 0.00 70 F 80 C steam generator K

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

3. Cut A, B & C 8/G Upper Assembly 6,318 131379 !25.40 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 divide". plate & channel head 1,722 5,087 97.14 0.00 72.07 Ai B & C S/G - Rig t'o 58'lev tion

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 A, B & C S/G

8. Lift A, B & C S/G U.A., invert,and 525 2,143 6.75 0.00 11.79 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 ~B (Continued)

SURGERY OP REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 4 MARCH 1982 TO 7 APRIL 1982 TURKEY POINT UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED ABOR EXPENDED ESTIMATED FOR REPORT NG EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DA ."; EXPOSURE PERIOD TO-DATE (C-COMPLETE)

(PERSON-i(OURS) (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 A, B & C S/G

12. Remove miscei.laneous piping from 1>410 6>050 17.62 0.00 29.79 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 ter'porary pover 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 'ngoing decon activities/remove and - 14,500 2>914 62.40 0.00 16.57 dispose contaminated materials 17 . Miscellaneous Activities 33>900 5>103 221.93 0.00 31.00 TOTAL PHASE II 69>129 61>252 1016.00 0.00 552.48

0 TABLE 3C

SUMMARY

OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 4MARCH 1982 TO 7 APRIL 1982 TURKEY POINT " UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTLMATED 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 PROCR.SS)

1. Inst llation of A, B & C S/G 17)540 61534 73.70 0.00 9.81 C Upp'er Assembli es

2. Weld Preparation of h, B & C 840 4,552 7.71 0.00 69.09 S/G Channel Head Remnants

3. Installation and Welding of 8)360 182.00 0.90 382.64 A, B & C S/Q Lower Assemblies 35,38'1068

4. Installation of A, B & C S/G 1,250 5.50 0.00 4.16 Main Steam Piping 5, Installation of A, B & C S/G 1,680 4,892 6.80 0.00 15.71 Fecdwater Pipirg

6. Welding of A, B & C S/G 1,554 5,479 15.10 0.00 119.86 Divider Plates

7. Install Insulation A, B & C 3,486 25,393 29.40 33.67 85.72 Steam Generators

8. Maintain Temporary Power, 21850 6,301 65.00 0.00 13.99 Lighting and Electrical Cables

9. Maintain/Erect/Rer ove Scaffolding 2,840 9,794 21.80 0.00 31.81

10. Ongoing Decon Activities/ 14,500 12,280 62.40 0.00 66.19 Rcmove/Dispose Contaminated Materials

ll TABLE 3C (Continued)

Sb~f.'KRY OF INSTA'ATION ACTIVITY EX!!OSJRFS REPORTING PERIOD 4 tARCH 1982 TO 7 APRIL 1982 TUR/EY POINT UN T 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR BXPENDED ESTll'~TED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-.DA E (C-COMPLETE)

(PERSON"HOURS) (PERSON"HOURS) (P~RSON-S~>>) (PERSON-R"H) (PERSOr -REH) (I"IN PROGRESS)

11. Miscellaneous Activities 27,190 22,699 174.59 0.00 100.60 C TOTAL PHASE III 82>000 135,373 644.00 34.57 899.58

il TABLE 30

SUMMARY

OF POST-INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 4 MARCH 1982 TO 7 APRIL 1982 TURKEY POINT " UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIViTY ESTIMATED LABOR EXPENDED ESTIKKTED 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)

l. Installation of concrete stop logs, 5,490 3,378 22,00 1.16 8.52 C concrete forms, rebar and pouring of new concrete 30'6" and 58'levation

2. Installation of miscellaneous 350 11,211 8.00 1.86 54.21

~

piping in S/G cubicles

3. Installation of emergency 310 58 3.00 0.00 0.22 containment coolers, control rod drive mechanism cooler and fans

4. Installation of miscellaneous 600 14,018 2.00 9.19 36.06 steel

5. Installation of A, B 6 C reactor 866 0 00 F 0.00 3.17 coolant pump motors

6. Removal of steam generator 500 663 1.00 0.00 1.19 transfer bridge

7. Installation of permanent electrical . 5SO 2,033 6.00 0.01 7.52 cables, equipment.

8. Removal o temporary containments 970 2,714 12.00 0.09 5 ~ 26 c and ventilation systems

9. Removal of temporary shielding 84 818 2.00 0.82 11.94

~ I ~

0 il ~ l1 TABLE 3D (Continued)

SUYil~ARY OF POST"INSTALLATION ACTIVITY EXPOSURES REPORTiNG PERIOD 4 ARCH l 982 TO 7 APRIL 1982 TURKEY PO'NT UNIT 3 ACTUAL ACTUAL EXPOSURE ACTUAI EXPOSUP~ ACTIVITY ESTI HATED LABOR EXPENDED ESTIMATED FOR REPGRTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPO O'K PERIOD TO-DAT. (C-CONPLETE)

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

10. Removal of scaffolding all levels 830 11,710 8.00 12.79 47.96

11. Ongoing decon activities/removal/ 3,630 14,273 15.00 )7.97 78.65 disposal contaminated materials

12. Reactor preparation/hot functional 1>265 0.00 14.32 53.21 testing

13. Tube cleaning/inspection A, B 6 C 1)290 0.00 0.00 .23. 83 S/Gs 14, Niscellaneous Activities 8,130 26)784 62.00 18.45 120.09 TOTAL PHASE IV 21)474 911081 141.00 76 .66 451,83

~ ~

0 E, ~

Is (P

TABl.K 4 PERSONNEL EXPOSURE SU'O'LAZY PER PHASE REPORTING PERIOD 4 MARCH 1982 TO 7 APRIl. 19S2 TURKEY POIilT UNIT 3 TOTAL ESTIMATED ACTUAL EXPOSURE PHASE STATUS PHASE ESTIMATED LABOR ACTUAL LABOR ESTIMATED EXPOSIE FOR REPORTING ACTUAL EXPOSVR"" (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-RKM) (PERSON-R""M) (PERSON-REM) (NS-NOT STARTED)

Preparation 34,992 31,787 283 283 0.00 247.94 Re=oval 69,129 611252 11016 1,016 0.00 552.48 Installation Miscellancousa 82)000 21$ 474 135,373 91,081 644 141 644 141 34.57 76.66 899.58 451.83 c

~

Project totals 207,595 319)493 2,084 2,084 111.23 2,151.83 aMiscellancous (post-installation) includes cleanup, storage and niscellaneous preparations prior to start-up.

~ ~ ~

0 '

T.hotii 5 SU.')')MARY OF RADiOACTIVE EI FL'i!EYT RFLEASES BEPORTIYC PERIC)D 0 '.lA!<CI". 1982 TO 7 A! RIL 19S2 ~ 0, TURKEY PO!AT - UYi!T 3 1982 I. LIQUID EFFLUE)4T RADIOACTIVITYRELEASED!N LIQUID EFFLUEKTS RE'ASES (CURIES)

TOTAL ACT!VITY TOTAL RELEAS" D THIS RELEASED DURIYG INARCH APRIL REPORTING S/C REPAIR iSOTOPE 3/O-3/3I q/I-~/7 PERIOD TO DATE Co-57 I.33E-Gv'.2!

Co-58 183r".-03 2.6(lE-05 i.46E-03 E-02 Co-.60 ') i )= r3

~

2.35E-05 2.25E-G3 4.16E 02 Cs-! 30 1.3o"-0>> 1.36r- 00 1.99E-G3 Cs-i37 1.3E-G6 3.>>9E-GO 3.96E-G3 Fe-59 3>>SE-G>>'.17E-05 0.33E-G>>

i)Aa-5a 7.17E-05 2.21E-03 "n-65

!3)

Yv-95 3 5v 0'k Sb-I20 '.'6rE-05 4.!6E-G5 3s97E Sb-125 1.50E-GO  !.S>>r-0>> 7 87r- 03

'-!! Cm 2.58rE-GC 2.8E-05 ') ol

~

~ I) r4

~ v>> E-03 ir-95 >>.06E-05 4.06E-05 8.7C'E-0>>

TOTAL <.7 li. -03 5>>OF.-05 0.76E-G i 9). 01 VOLL:!)'E RELEAS" D VO,IL RE'ASr D

'quio E.'ll e~. Volume TH!S aiEPORTI)XC DURiiXG S/G REPA!R Pele" sec ('ters) 8.! CE 05 3.26E+0'i PERiOD TO DATE 8.07E+05 I.G I Ei07

+No; ce. ctable

\

TABLE 5 (Continued)

SUMMARY

OF RAD!OACT! VE EFF'ENT R!:.LEASES MA!HACH

~

0 ~

R EPORT!i'JG PERIOD 0 1982 TO 7 APRIL 1982 TURKEY PONT - UNIT 3 1982 I. A!RBORiXE RADIOACTIVITYRELEASFD N AIRBORNE EFFLUENTS RELEASES (CURIES)

TOTAL ACTIVITY TOTAL A. YOBLE GASES RELEASED THIS RELEASED DURING MARCH APRIL REPORTING S/G REPAIR ISOTOPE 3/4-3/31 0/I-O/7 PERIOD TO DATE Kr-87 Kr-88 Xe-133 Xe-l33m Xe-135 Xe-138 B. HALOGEiNS 1-13!

!-133 TOTAL

+Not Detectab!e

'E I~ F,i.< )

0

TABL.E 5 (Cor.tinued)

SUMMARY

OF RADIOACTIVE FFFLUEiVT RELEASES REPORTliVG PERIOD 0 MARCH 1982 TO 7 APRIL 1982 TUikiYEY PO!NT - UiVIT 3 1982 I. P.IR BOR NF RADIOACTIVITYRELEASED IN AIRBORNE EFFLUENTS RELEASES (CURIFS)

TOTA'L ACTIVITY TOTAL C. PARTICULATES RELEASED THIS RELEASED DURIiVG MARCH APRIL REPORTING S/G REPAIR ISOTOPE 3/0-3/31 O/I-O/7 PERIOD TO DATE Ce-IVI Ce-100 Co-58 2.30E-05 Co-60 7.7E-07 7.7E-07 1.79E-OV I.S7E-06 Cs-13's-137 8.38E-06 Fe-59 Mn-50 7.63E-O7 Zn-65 iVb-95 1.15E-07 TOTAL 7.7E-07 7.7E-07 2.ICE-O'-:

+Not Detectable

~ ~

~

IJ /k t, w Ci a,r I 30 TABLE 6

SUMMARY

OF SOLID LOW-LEVEL RADIOACTIVE WASTE REPORTING PERIOD 0 MARCH 1982 TO 7 APRIL 1982 TURKEY POINT - UNIT 3 I. SOLID LOW-LEVEL RADIOACTIVE WASTE GENERATED FROM U-3 S/G REPAIR WASTE FORM VOLUME LLWa IN CU-FT VOLUME LLW IN CU-FT FOR REPORTING PERIOD TO DATE Compacted Dry Active Waste 2,625 21,210 Non-Compacted Dry Active Waste 100 0,955 Resin and Filter Media 75 1,690 Channel Head Decontamination Waste 717.5 Miscellaneous 2/775 Totals 2,800 31,307.5 II. SOLID LOW-LEVEL REPAIR ACTIVITYWASTE SHIPPED REPORTING PERIOD VOLUME LLW SHIPPED ESTIMATED ACTIVITY DATES 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 0 March 82 - 7 April 82 2,200 2.71 Project Totals 28,765 02.20 a LLW Low-level (radioactive) waste.

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

P

\pl J,'~A