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| issue date = 04/29/1983
| issue date = 04/29/1983
| title = Forwards Third Radiological Progress Rept for Steam Generator Repair Program
| title = Forwards Third Radiological Progress Rept for Steam Generator Repair Program
| author name = UHRIG R E
| author name = Uhrig R
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name = VARGA S A
| addressee name = Varga S
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000251
| docket = 05000251
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:i I'REGULATOR NFORMATION DISTRIBUTION
{{#Wiki_filter:I i
'S EM ('RIDS)'ACCESSION,NBRt8305030166 DOC DATEt 83/04/29NOTARIZED:
                            'REGULATOR           NFORMATION DISTRIBUTION 'S             EM   ('RIDS)
NO DOCKET¹'FAGIL;.50
  'ACCESSION,NBRt8305030166                     DOC   DATEt     83/04/29 NOTARIZED: NO                 DOCKET ¹
'251 tTur key Po'fnt 1Pl anti',Uni;t 0iFlorida IPower-and Light"C 05000251'AUTH~NAME AUTHOR'AFFILIATION
    'FAGIL;.50 '251 tTur key Po'fnt           1Pl anti ',Uni;t 0i Florida IPower -and Light       "C 05000251
'UHRIGiR,E,:F 1 or ida iPower I Light Co, GREC IP~NAME REC IP IENT.'AF F IL'I ATION VARGAP'S,AB Operating Reactons Branch 1 1'
      'AUTH ~ NAME               AUTHOR     'AFFILIATION
    'UHRIGiR,E,:F                 1 or ida iPower   I Light Co, GREC IP ~ NAME             REC IP IENT. 'AF F IL'IATION VARGAP'S,AB                     Operating Reactons Branch               1 1


==SUBJECT:==
==SUBJECT:==
.Forwards<<thir d radiological-'progress rept"for ssteam jgener ator irepair'r ograms" DISTRIBUTION
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'CODE: 'A001'0)COPIES RECEIYED:I TR.$'lENCL.J" SIZE:.tTITLE t OR"Submi't ta 1: 1Gener a l Di st r i but i on NOTES!RECIPIENT ID CODE/NAME NRR ORB1 BC 01 RECOPIES LTTR'ENCL"7 7 RECIPIENT ID CODE/NAME iCOPIES LT)TR ENCL INTiERNALt ELD/HDS4 NRR/DL DIR-DS--ETB.REG ILE OQ 1 0 1 1.1 1 NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN2 1 1 1~1 1 0 1.EXTERNALs ACRS'NRC:PDR NT I'=09*02'.l6 I 6 1 1 1 1 LPDR NSIC 03 05)TOTAL, NUMBER, OF'."COPIES'EQUIRED:
SIZE:.
LTTR 25 ENCL 23  
tTITLE t OR "Submi't ta 1: 1Gener a l Di st r but i on   i RECOPIES NOTES!
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g<lilt~gQ, l'j"JQ'3)j I'y i'lJ Of 4~Wg"<~X"~~E~l~l);jC-]I),')l 3l>~J])'1)))'f)(,g ,4 fl', Pffft.''f O.BOX 14000, JUNO BEACH, FL 33408'sg FLORIDA POWER 5 LIGHT COMPANY April 29, 1983 L-83-272 Office of Nuclear Reactor Regulation Attention:
  )TOTAL, NUMBER, OF'."COPIES'EQUIRED:                   LTTR       25   ENCL   23
Mr.Steven A.Varga, Chief Operating Reactors Branch gl Division of Licensing U.S.Nuclear Regulat'ory Commission Washington, D.C.20555


==Dear Mr.Varga:==
(                                                                                                                                                                          ~ ~
I Re: Turkey Point Unit 4 Docket No.50-251 Steam Generator Repair Program-Radiolo ical Pro ress Re ort-No.3 Please find attached our thi"rd Radiological Progress Report for the Steam Generator Repair Program as required by Section 3.H.(2)(c) of DPR-41.Very truly yours, Robert E.Uhrig'ice President Advanced Systems&Technology REU/PLP/cab Attachment cc: J.P.O'Reilly, Region II Harold F.Reis, Esquire 8305030ih8 8S0yg9 PDR IIIIDOCK 0500025i R PDR..~...PEOPL'E...
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SERVING PEOPLE 0 I TABLE OF CONTENTS PAGE NO.1.0'NTRODUCTION
fi' T'"
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==2.0 OCCUPATIONAL==
O. BOX 14000, JUNO BEACH, FL 33408
RADIATION EXPOSURE 2.1 General 2.2 Description and Format of Exposure Data 2.3 Discussion of Exposure Results 2 3 3.0 APPLICATION OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES)
                                                                                                    'sg FLORIDA POWER 5 LIGHT COMPANY April 29,      1983 L-83-272 Office of Nuclear Reactor Regulation Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch gl Division of Licensing U. S. Nuclear Regulat'ory Commission Washington, D.C. 20555


===3.1 General===
==Dear  Mr . Varga:==
3.2 Contamination Control Envelopes and Ventilation


===3.3 Installation===
I Re:    Turkey Point Unit 4 Docket No. 50-251 Steam Generator Repair Program
of Steam Generator Lower Assemblies(SGLAs) 3.0 3.5 3.6 Welding of Steam Generator Divider Plates Reactor Head Preparation for Hot Functional Testing General Techniques and Practices 5 5 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General 0.2 Liquid Releases 0.3 Airborne Releases 0.0 Solid Radioactive Waste 6
        - Radiolo ical Pro ress Re ort - No.         3 Please    find attached      our thi"rd Radiological Progress Report for the Steam Generator Repair Program as required by Section 3.H.(2)(c) of DPR-41.
Very  truly yours, Robert E. Uhrig President    'ice Advanced Systems        & Technology REU/PLP/cab Attachment cc:    J. P. O'Reilly,      Region  II Harold F. Reis, Esquire 8305030ih8 8S0yg9 PDR IIIIDOCK R
0500025i PDR..   ~    ...
PEOPL'E... SERVING PEOPLE


==5.0 CONCLUSION==
0 I TABLE OF CONTENTS              PAGE NO.
S AND OBSERVATIONS TABLES TABLE 1 TABLE 2 TABLE 3A TABLE 3B TABLE 3C TABLE 3D TABLE 0 TABLE 5 TABLE 6 Description of Major Tasks Personnel Exposure Summary-Per Task Summary of Preparatory Activity Exposures Summary of Removal Activity Exposures Summary of Installation Activity Exposures Summary of Post-Installation Activity Exposures Personnel Exposure Summary-Per Phase Summary, of Radioactive Effluent Releases Summary of Solid Low Level Radioactive Waste Shipments 9 11 13 16 19 21 20 25 28  
1.0 'NTRODUCTION 2.0    OCCUPATIONAL RADIATIONEXPOSURE 2.1 General 2.2 Description and Format of Exposure Data                    2 2.3 Discussion of Exposure Results                            3 3.0    APPLICATION OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES) 3.1 General 3.2 Contamination Control Envelopes and Ventilation 3.3 Installation of Steam Generator Lower Assemblies(SGLAs) 3.0 Welding of Steam Generator Divider Plates 3.5 Reactor Head Preparation for Hot Functional Testing        5 3.6 General Techniques and Practices                          5 0.0    RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General 0.2 Liquid Releases                                            6 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                 16 TABLE 3C    Summary   of Installation Activity Exposures             19 TABLE 3D    Summary   of Post-Installation Activity Exposures       21 TABLE 0    Personnel   Exposure Summary - Per Phase                 20 TABLE 5    Summary, of Radioactive Effluent Releases                 25 TABLE 6    Summary of Solid Low Level Radioactive Waste Shipments   28


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


Radiological Progress Report No.3 contains information pertaining to the radiological aspects of the Unit 0 Steam Generator Repair Program (SGRP)for the period February 3, 1983 through March 30, 1983.This information includes the following:
Radiological Progress Report No. 3 contains information pertaining to the radiological aspects of the Unit 0 Steam Generator Repair Program (SGRP) for the period February 3, 1983 through March 30, 1983. This information includes the following:
a.An assessment and summary of the occupational exposure and labor expended for each reporting period (throughout the project).b.An evaluation of the effectiveness of dose reduction techniques (ALARA principles).
: a. An assessment and summary of the occupational exposure and labor expended for each reporting period (throughout the project).
F c.An estimate of the radioactivity released in liquid and airborne effluents.
: b. An evaluation of the effectiveness of dose reduction techniques (ALARA principles).                               F
d.An estimate of the solid radioactive waste generated including volume and radioactive content.Significant project.tasks performed during this reporting period included: 1.Removal of steam generator transfer bridge.2.Installation of main steam and feedwatez piping.3.Complete installation of steam generator upper and lower assemblies.
: c. An estimate   of the radioactivity released in liquid and airborne effluents.
5.6.Welding of steam generator divider plates./Inspection and close-out of'steam generators in preparation for testing.l Installation of insulation on steam genet ators.7.Installation of miscellaneous piping in, steam generator cubicles.8.Installation of miscellaneous steel.9.Installation of reactor coolant pump motors.10.Installation of emergency containment coo'lers, control rod drive mechanism coolers and fans.11.Installation of concrete stop logs, concrete forms, rebar and pouring of new concrete.12.Preparation for and conducting of hot functional testing.13.Cleanup activities (removal of scaffolding and support equipment, removal of temporary shielding).
: d. An estimate of the solid radioactive waste generated including volume and radioactive content.
Significant project. tasks performed during this reporting period included:
: 1. Removal of steam generator transfer bridge.
: 2. Installation of main steam and feedwatez piping.
: 3. Complete installation of steam generator upper and lower assemblies.
Welding of steam generator divider plates.
5.
                                                      /
Inspection and close-out of'steam generators in preparation for testing.
l
: 6. Installation of insulation on steam genet ators.
: 7. Installation of miscellaneous piping in,steam generator cubicles.
: 8. Installation of miscellaneous steel.
: 9. Installation of reactor coolant pump motors.
: 10. Installation of emergency containment coo'lers, control rod drive mechanism coolers and fans.
: 11. Installation of concrete stop logs, concrete forms, rebar and pouring of new concrete.
: 12. Preparation for and conducting of hot functional testing.
: 13. Cleanup activities (removal of scaffolding and support equipment, removal of temporary shielding).
Several on-going activities also performed during this period included: cleanup and decontamination,'aintenance of temporary electrical power and lighting services, surveillance of temporary shielding, health physics support and project supervision.
Several on-going activities also performed during this period included: cleanup and decontamination,'aintenance of temporary electrical power and lighting services, surveillance of temporary shielding, health physics support and project supervision.
I


==2.0 OCCUPATIONAL==
I 2.0 OCCUPATIONAL RADIATIONEXPOSURE 2.1   General As indicated in Radiological Progress Report No. 1, occupational exposure to radiation may'e considered the major radiological impact of the SGRP. The program developed to collect exposure information and provide accurate           "
RADIATION EXPOSURE 2.1 General As indicated in Radiological Progress Report No.1, occupational exposure to radiation may'e considered the major radiological impact of the SGRP.The program developed to collect exposure information and provide accurate assessments of tasks performed is discussed in detail in Section 2.1-2.3 of" Radiological Progress Report No.1.This program was utilized throughout this reporting period.-A description of the thirteen (13)major tas'<s.", indicated in Table 1.2.2 Descri tion and Format of Ex osure Data Table 2 presents a summary of the occupational radiation exposure expended in person-rem and the labor expended in the radiation field in person-hours through this reporting period (i.e., from project commencement on 10 October 1982 to 30 March 1983).+Also included are the original estimated expenditures.
assessments of tasks performed is discussed in detail in Section 2.1 2.3 of Radiological Progress Report No. 1. This program was utilized throughout this reporting period. -A description of the thirteen (13) major tas'<s .", indicated in Table 1.
The following comments are provided for clarification and should be considered when reviewing the data presented in Table 2.ao b.Co 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.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.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.d.Task items indicating no accumulated exposures have not commenced during this reporting period.A detailed summary of the personnel exposure expended through this reporting period for preparatory, removal, installation and post-installation activities is presented in Tables 3A, 3B, 3C and 3D respectively.
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 10 October 1982 to 30 March 1983).+ Also included are the original estimated expenditures. The following comments are provided for clarification and should be considered when reviewing the data presented in Table 2.
This summary includes both the labor and exposure expenditures and the original estimated expenditures.
ao     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.
These tables list a more detailed breakdown of specific job activities which have been incorporated into+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).
: 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.
Therefore, accumulated dose is reported conservatively.
Co    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.
g 0 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.
: d. Task items indicating no accumulated exposures have not commenced during this reporting period.
'The following comments are provided for clarification and should be considered when reviewing the data presented in Tables 3A, 3B, 3C, 3D and 0.ao b.Activity status indications are given to allow comparison of actual versus estimated person-rem expenditures.
A detailed summary of the personnel exposure expended through this reporting period for preparatory, removal, installation and post-installation activities is presented in Tables 3A, 3B, 3C and 3D respectively. This summary includes both the labor and exposure expenditures and the original estimated expenditures. These tables list a more detailed breakdown of specific job activities which have been incorporated into
Activities indicated as in progress may require additional exposure prior to completion of the activity;therefore, a valid comparison't this time is not justified.
+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.
Co For completed activities, it should be noted that a small amount of additional exposure and labor may appear sometime after completion is indicated, as a result of such factors as: field changes to procedures, work involving activity related to support equipment, localized work area cleanup, etc.d.Some activities were not estimated in the SGRR and have no estimated labor and'xposure values indicated.
Historically, SRPD results are higher than TLD results primarily due to drift (caused by factors such as heat and humidity, and initial charging). Therefore, accumulated dose is reported conservatively.
These activities are controlled by RWP's which have an exposure estimate for the activity for purposes of exposure"tracking".
 
0 g


===2.3 Discussion===
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.
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 60%of the original total estimate.Table 2 actual exposures are recorded by computer acquisition as discussed in Progress Report No..l.Table 2 includes all exposure expended through March 30, 1983 and will continue to be used for accumulation of all personnel exposures through project completion.
ao    Activity status indications are given to allow comparison of actual versus estimated person-rem expenditures.
The exposure expended to date is primarily attributed to repair project preparator'y, removal, installation and post-installation activities as indicated in', Tables 3A, 3B, 3C, 3D and 0.As discussed in Progress Report No.2, Tables:3A and 3B.show that the total actual exposure expended for preparatory and removal phase activities was approximately 5196 less than the total estimated exposures for those activities.
: b. Activities indicated as in progress may require additional exposure prior to completion of the activity; therefore, a valid comparison't this time is not justified.
Table 3C shows that the total occupational exposure accumulated for installation phase activities gras approximately 563 person-rem as compared to the original exposure estimate of 600 person-rem.
Co    For completed activities, it should be noted that a small amount of additional exposure and labor may appear sometime after completion is indicated, as a result of such factors as: field changes to procedures, work involving activity related to support equipment, localized work area cleanup, etc.
The exposure attributed to steam generator lower assembly installation (approximately 227 person-rem) was greater than the estimate of approximately 200 person-rem (item 2 and 3 of Table 3C).The exposure attributed to welding steam generator divider plates (approximately 59 person-rem) was significantly higher than the estimate of 15 person-rem (item 0 of Table 3C).Table 3D shows that the total occupational exposure accumulated for post-installation phase activities in progress is approximately 56 person-rem as compared to the original exposure estimate of 141 person-rem.
: d. Some  activities were not estimated in the SGRR and have no estimated labor and values indicated. These activities are controlled by RWP's which have  'xposure an  exposure estimate for the activity for purposes of exposure "tracking".
The information for all phase activities in progress or completed (as shown in Tables 3A, 3B, 3C and 3D)is summarized in Table 0.The total exposure expended during this reporting period was approximately 367 person-rem.  
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 60% of the original total estimate. Table 2 actual exposures are recorded by computer acquisition as discussed in Progress Report No..l. Table 2 includes all exposure expended through March 30, 1983 and will continue to be used for accumulation of all personnel exposures through project completion. The exposure expended to date is primarily attributed to repair project preparator'y, removal, installation and post-installation activities as indicated in', Tables 3A, 3B, 3C, 3D and 0.
As discussed in Progress Report No. 2, Tables:3A and 3B.show that the total actual exposure expended for preparatory and removal phase activities was approximately 5196 less than the total estimated exposures for those activities.
Table 3C shows that the total occupational exposure accumulated for installation phase activities gras approximately 563 person-rem as compared to the original exposure estimate of 600 person-rem. The exposure attributed to steam generator lower assembly installation (approximately 227 person-rem) was greater than the estimate of approximately 200 person-rem (item 2 and 3 of Table 3C). The exposure attributed to welding steam generator divider plates (approximately 59 person-rem) was significantly higher than the estimate of 15 person-rem (item 0 of Table 3C).
Table 3D shows that the total occupational exposure accumulated for post-installation phase activities in progress is approximately 56 person-rem as compared to the original exposure estimate of 141 person-rem.
The information for all phase activities in progress or completed (as shown in Tables 3A, 3B, 3C and 3D) is summarized in Table 0. The total exposure expended during this reporting period was approximately 367 person-rem.


==3.0 APPLICATION==
3.0 APPLICATION OF DOSE REDUCTION TECHNI UES (ALARA PRINCIPLES) 3.1    General This section discusses the techniques and practices which have been effective in providing dose reductions to personnel during the reporting period. Where available data permits, the following evaluations include a quantitative assessment of the person-rem savings which can be attributed to the techniques use/a 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 lower assemblies which included divider plate welding. Welding and other operations associated with steam generator lower assembly installation resulted in low-level airborne radioactivity which was effectively controlled with the filtered ventilation system. At times, particularly during divider plate welding, it was necessary to install the filtered exhaust ductwork in the channel head with the work crews to provide 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.
OF DOSE REDUCTION TECHNI UES (ALARA PRINCIPLES)
3.3    Installation of Steam Generator Lower Assemblies (SGLAs)
Installation of the new SGLAs was completed during this reporting period.
Exposure reduction techniques utilized for SGLA installation were discussed in Radiological Progress Report No. 2.
The exposure expended for installation of the SGLAs was approximately 227 person-rem as compared to the estimate of approximately 200 person-rem (item 2 and 3 of Table 3C). Without the benefit of decontamination and channel head shielding, the exposure would be approximately 5675 person-rem. Thus a conservative exposure savings of approximately 5450 person-rem was realized.
3.0    Weldin of Steam Generator Divider Plates Exposure reduction techniques similar to those techniques utilized during steam generator lower assembly installation (discussed in Radiological Progress Report No. 2) were employed during welding of the steam generator divider plates.
These techniques included:
aO    Controlling access/egress to steam generator 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.
Co    Utilizing filtered ventilation ducting to exhaust low-level airborne radioactivity from the work area.
: d.      Use  of channel head shielding whenever practical to reduce exposure rates during welding and repair operations.
The exposure expended for installation of the steam generator divider plates was approximately 59 person-rem as compar'ed to the estimate of approximately 15 person-rem (item 0 of Table 3C). V/ithout the benefit of channel head shielding and decontamination, the exposure expended would be approximately 1500 person-rem. Thus, a conservative savings of 'approximately 1000 person-rem was realized.
3.5  Reactor Head Pre aration for Hot Functional Testin Hot functional operations were in progress at the close of this reporting period.
Certain pre-hot functional and post-hot functional testing activities will have the benefit of shielding. These activities include the following work on the reactor head:
1;    Installation and removal of instrument port conoseals.
: 2. Detensioning and tensioning of the reactor head.
: 3. Installation and removal of reactor head studs.
A report on the exposure savings realized as a result of reactor head shielding will be discussed in a subsequent report when-all activities associated wittithe hot functional test are completed.
. 3.6  General, Techni ues and Practices In addition  to the assessment of dose reduction techniques described above, it is important to note some of the more general techniques 'and practices employed to maintain adequate control of personnel radiation exposure. These practices include the following:
a)    A comprehensive health physics program which includes an extensive training and radiological surveillance program.
b)    Use  of repair project process sheets.
c)    Utilization of "in-containment" low-lev'el 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)    Controlled access to containment tool cribs and weld rod rooms. A detailed description of these techniques and practices are discussed in Progress Report No. 1.


===3.1 General===
I I h)    Use of a cooler. system in the Reactor. Containment Building (RCB) to improve worker comfort. Although this system was not designed to cool the entire RCB, it significantly improved worke; comfort especially on the where a large majority of the work~ was scheduled.          58'levation A communications system used by Health Physics personnel and located in the vicinity of,each S/G enclosure to allow direct communication with the Health Physics Shift Supervisor. This system enables the health physics technician to maintain continuous communication with the shift supervisor thereby minimizing delays (and person-rem expended) on the job.
This section discusses the techniques and practices which have been effective in providing dose reductions to personnel during the reporting period.Where available data permits, the following evaluations include a quantitative assessment of the person-rem savings which can be attributed to the techniques use/a 3.2 Contamination Control Envelo es and Ventilation
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.
I)    Increased frequency of TLD readouts for purposes of obtaining actual exposure information for personnel working in the S/G channel heads and other relatively high exposure areas.
Quantitative assessments are difficult to develop for these "general" techniques and practices which contribute significantly to the overall ALARA commitment for the repair project. An update on these techniques and practices will be discussed in future reports.
0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General Radioactive effluents, comprised of liquid and airborne releases, and low-level solid radioactive waste produced during this reporting period and throughout the repair project to date are summarized in Tables 5 and 6 respectively.
Laundry operations continue to be the major volume of liquid releases for the Unit 0 SGRP. As shown in Table 5 the composition of radioactive isotopes detected remain relatively unchanged from those detected during the previous period. Approximately 00% of the total activity released to date (excluding tritium) was in the form of activated metals (e.g. Co-58, Co-60, Mn-50, Ag-110m). The remaining activity (excluding tritium) included the following radionuclides: Cs-137 (21%), Cs-130 (11%), Cs-136 (0.3%) and radioiodines (28%).
The total activity released (excluding tritium) to date is approximately 13% of the activity projected to be released for Unit No. 0 during the repair project (refer to Table 5.2-7 of the SGRR). The amount of tritium which has been released from SGRP activities, remains approximately 25% of the amount that was estimated'(Table 5.2-7 of the SGRR).
0.3 Airborne Releases Airborne releases for this reporting period originated primarily from continuous ventilation of the containment during repair activities. A summary of airborne releases is shown in Table 5. The particulates detected are typical of


===3.3 Enclosures===
radionuclides expected as a result of an extended shutdown. The total activity released to date that is attributed to repair project activities is approximately 18% of the total estimated activity projected to be released.
for contamination control and a filtered ventilation system were utilized during installation of the steam generator lower assemblies which included divider plate welding.Welding and other operations associated with steam generator lower assembly installation resulted in low-level airborne radioactivity which was effectively controlled with the filtered ventilation system.At times, particularly during divider plate welding, it was necessary to install the filtered exhaust ductwork in the channel head with the work crews to provide adequate ventilation in the work area.Contamination control enclosures were modified as needed to maximize channel head accessibility.
0A Solid Radioactive Waste A summary of low level radioactive waste (LLW) shipments from Unit 0 during the reporting period is provided in Table 6. The amount of LLW which had been packaged but not shipped prior to the close of the period is also provided. The LLW shipments during this reporting period were made to both the Barnwell, South Carolina and Richland, Washington Low-Level Waste Disposal Facilities.
These modifications assured positive personnel access control as well as controlling the spread of relatively higher levels of contamination to surrounding areas.Installation of Steam Generator Lower Assemblies (SGLAs)Installation of the new SGLAs was completed during this reporting period.Exposure reduction techniques utilized for SGLA installation were discussed in Radiological Progress Report No.2.The exposure expended for installation of the SGLAs was approximately 227 person-rem as compared to the estimate of approximately 200 person-rem (item 2 and 3 of Table 3C).Without the benefit of decontamination and channel head shielding, the exposure would be approximately 5675 person-rem.
The majority of the waste volume shipped was compactable and non-compactable dry active waste.
Thus a conservative exposure savings of approximately 5450 person-rem was realized.3.0 Weldin of Steam Generator Divider Plates Exposure reduction techniques similar to those techniques utilized during steam generator lower assembly installation (discussed in Radiological Progress Report No.2)were employed during welding of the steam generator divider plates.These techniques included: aO Controlling access/egress to steam generator 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.Co Utilizing filtered ventilation ducting to exhaust low-level airborne radioactivity from the work area.
The total volume of solid LLW generated due to repair project activities through this reporting period (excluding the SGLA's) is approximately 25% greater than the total volume estimated in the Gould Affidavit dated 3une 12, 1981. It should.
d.Use of channel head shielding whenever practical to reduce exposure rates during welding and repair operations.
be noted that the volume of waste shipped is less than the accumulated volume of waste generated. This can be primarily attributed to additional volume reduction techniques used prior to shipment, which are not accounted. for when initially generated. The total quantity of radioactivity shipped through this reporting period as a result of the Unit 0 SGRP was less than 09% of the activity estimated in the SGRR. The remaining LLW.generated is expected to be-expeditiously shipped to a licensed burial facility.
The exposure expended for installation of the steam generator divider plates was approximately 59 person-rem as compar'ed to the estimate of approximately 15 person-rem (item 0 of Table 3C).V/ithout the benefit of channel head shielding and decontamination, the exposure expended would be approximately 1500 person-rem.
Thus, a conservative savings of'approximately 1000 person-rem was realized.3.5 Reactor Head Pre aration for Hot Functional Testin Hot functional operations were in progress at the close of this reporting period.Certain pre-hot functional and post-hot functional testing activities will have the benefit of shielding.
These activities include the following work on the reactor head: 1;Installation and removal of instrument port conoseals.
2.Detensioning and tensioning of the reactor head.3.Installation and removal of reactor head studs.A report on the exposure savings realized as a result of reactor head shielding will be discussed in a subsequent report when-all activities associated witti the hot functional test are completed.
.3.6 General, Techni ues and Practices In addition to the assessment of dose reduction techniques described above, it is important to note some of the more general techniques
'and practices employed to maintain adequate control of personnel radiation exposure.These practices include the following:
a)A comprehensive health physics program which includes an extensive training and radiological surveillance program.b)Use of repair project process sheets.c)Utilization of"in-containment" low-lev'el 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)Controlled access to containment tool cribs and weld rod rooms.A detailed description of these techniques and practices are discussed in Progress Report No.1.
I I h)Use of a cooler.system in the Reactor.Containment Building (RCB)to improve worker comfort.Although this system was not designed to cool the entire RCB, it significantly improved worke;comfort especially on the 58'levation where a large majority of the work~was scheduled.
A communications system used by Health Physics personnel and located in the vicinity of, each S/G enclosure to allow direct communication with the Health Physics Shift Supervisor.
This system enables the health physics technician to maintain continuous communication with the shift supervisor thereby minimizing delays (and person-rem expended)on the job.j)Multi-badging for evaluation of personnel exposure for those tasks performed in relatively complex radiation fields.k)Use of temporary lead shielding in high occupancy/traffic areas.I)Increased frequency of TLD readouts for purposes of obtaining actual exposure information for personnel working in the S/G channel heads and other relatively high exposure areas.Quantitative assessments are difficult to develop for these"general" techniques and practices which contribute significantly to the overall ALARA commitment for the repair project.An update on these techniques and practices will be discussed in future reports.0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General Radioactive effluents, comprised of liquid and airborne releases, and low-level solid radioactive waste produced during this reporting period and throughout the repair project to date are summarized in Tables 5 and 6 respectively.
Laundry operations continue to be the major volume of liquid releases for the Unit 0 SGRP.As shown in Table 5 the composition of radioactive isotopes detected remain relatively unchanged from those detected during the previous period.Approximately 00%of the total activity released to date (excluding tritium)was in the form of activated metals (e.g.Co-58, Co-60, Mn-50, Ag-110m).The remaining activity (excluding tritium)included the following radionuclides:
Cs-137 (21%), Cs-130 (11%), Cs-136 (0.3%)and radioiodines (28%).The total activity released (excluding tritium)to date is approximately 13%of the activity projected to be released for Unit No.0 during the repair project (refer to Table 5.2-7 of the SGRR).The amount of tritium which has been released from SGRP activities, remains approximately 25%of the amount that was estimated'(Table 5.2-7 of the SGRR).0.3 Airborne Releases Airborne releases for this reporting period originated primarily from continuous ventilation of the containment during repair activities.
A summary of airborne releases is shown in Table 5.The particulates detected are typical of radionuclides expected as a result of an extended shutdown.The total activity released to date that is attributed to repair project activities is approximately 18%of the total estimated activity projected to be released.0A Solid Radioactive Waste A summary of low level radioactive waste (LLW)shipments from Unit 0 during the reporting period is provided in Table 6.The amount of LLW which had been packaged but not shipped prior to the close of the period is also provided.The LLW shipments during this reporting period were made to both the Barnwell, South Carolina and Richland, Washington Low-Level Waste Disposal Facilities.
The majority of the waste volume shipped was compactable and non-compactable dry active waste.The total volume of solid LLW generated due to repair project activities through this reporting period (excluding the SGLA's)is approximately 25%greater than the total volume estimated in the Gould Affidavit dated 3une 12, 1981.It should.be noted that the volume of waste shipped is less than the accumulated volume of waste generated.
This can be primarily attributed to additional volume reduction techniques used prior to shipment, which are not accounted.
for when initially generated.
The total quantity of radioactivity shipped through this reporting period as a result of the Unit 0 SGRP was less than 09%of the activity estimated in the SGRR.The remaining LLW.generated is expected to be-expeditiously shipped to a licensed burial facility.


==5.0 CONCLUSION==
==5.0 CONCLUSION==
S AND OBSERVATIONS The total exposure expended for installation phase activities was.approximately 563 person-rem as compared to the estimate of Qt0 person-rem.
S AND OBSERVATIONS The total exposure expended for installation phase activities was. approximately 563 person-rem as compared to the estimate of Qt0 person-rem. Approximately 51% (286 person-rem) of the total exposure expended during the installation phase was attributed to the installation of the SGLAs.
Approximately 51%(286 person-rem) of the total exposure expended during the installation phase was attributed to the installation of the SGLAs.The exposure expended for post-installation, phase activities through this reporting period is approximately 56 person-rem as compared to the estimate of 101 person-rem.
The exposure expended for post-installation, phase activities through this reporting period is approximately 56 person-rem as compared to the estimate of 101 person-rem. As discussed in Section 2.2 of this report, several post-installation activities not originally estimated may result in the total exposure for the post-installation phase exceeding that estimate. The effect of these activities on the'otal exposure for the post-installation phase will be discussed in the next progress report.
As discussed in Section 2.2 of this report, several post-installation activities not originally estimated may result in the total exposure for the post-installation phase exceeding that estimate.The effect of these activities on the'otal exposure for the post-installation phase will be discussed in the next progress report.Table 0 shows that the total labor expended to date is approximately 21%above the total labor estimate projected for the Unit 0 SGRP.With clean-up and post-hot functional activities remaining, it is projected that the total actual labor for the Unit 0 SGRP will be approximately 28%above that originally estimated.
Table 0 shows that the total labor expended to date is approximately 21% above the total labor estimate projected for the Unit 0 SGRP. With clean-up and post-hot functional activities remaining, it is projected that the total actual labor for the Unit 0 SGRP will be approximately 28% above that originally estimated.
The total occupational radiation exposure expended to date is approximately 60%of the original total estimate.With project completion expected in early May, it is projected that the total exposure for the Unit 0 SGRP will be in the range of 1300 to 1000 person-rem.
The total occupational radiation exposure expended to date is approximately 60%
This exposure range is approximately 33%to 38%lower than the original total estimate for the Unit 0 SGRP.
of the original total estimate. With project completion expected in early May, it is projected that the total exposure for the Unit 0 SGRP will be in the range of 1300 to 1000 person-rem. This exposure range is approximately 33% to 38%
a)b)Radioactive liquid effluents released are well within the total estimate projected to be released in Table 5.2-7 of the repair report.The calculated activity (excluding t'ritium)is approximately 13%while the tritium activity is approximately 25%of the total estimated activity in the SGRR.Airborne releases of radioactivity attributed to repair project activities are below the estimates provided in the SGRR.The activity associated with airborne releases for the remaining portion of the repair project is not expected to exceed the estimate indicated in the SGRR since the remaining work to be performed as a result of the SGRP includes primarily clean-up and post-hot functional activities.
lower than the original total estimate for the Unit 0 SGRP.
c)Solid low level radioactive waste generated to date (excluding the SGLA's)for the Unit No.0 SGRP is approximately 25%greater than the estimate provided in the Gould Affidavit dated 3une 12, 1981.Some conservatism is employed in assigning the volume of waste generated to the Unit 0 SGRP even though some of the work was not directly related to the repair project.The total quantity of radioactivity shipped was below the activity estimated in the SGRR.Progress Report Number 0 will contain information from 30 March, 1983 through project completion (early May, 1983).This final report will also contain a summary for those tasks where the actual person-rem expended was significantly greater than the estimated values.This sumeKry will include a discussion of the lower expended exposure for the Unit 0 SGRP as compared to the Unit 3 SGRP and recommended changes in techniques and methods that should be evaluated to determine their effects on further reducing exposure for steam generator replacement
 
-channel cut method.
a)   Radioactive liquid effluents released are well within the total estimate projected to be released in Table 5.2-7 of the repair report. The calculated activity (excluding t'ritium) is approximately 13% while the tritium activity is approximately 25% of the total estimated activity in the SGRR.
I  
b)    Airborne releases of radioactivity attributed to repair project activities are below the estimates provided in the SGRR. The activity associated with airborne releases for the remaining portion of the repair project is not expected to exceed the estimate indicated in the SGRR since the remaining work to be performed as a result of the SGRP includes primarily clean-up and post-hot functional activities.
~~TABLE 1 DESCRIPTION OF MA3OR TASKS TASK TASK DESCRIPTION 1.Concrete and structural steel removal and placement.
c)   Solid low level radioactive waste generated to date (excluding the SGLA's) for the Unit No. 0 SGRP is approximately 25% greater than the estimate provided in the Gould Affidavit dated 3une 12, 1981. Some conservatism is employed in assigning the volume of waste generated to the Unit 0 SGRP even though some of the work was not directly related to the repair project. The total quantity of radioactivity shipped was below the activity estimated in the SGRR.
'2.Construction of pedestal cranes, preparation of polar crane, miscellaneous cribbing platforms, S/G transfer bridge..3.Removal, modification and reinstallation of S/G upper assemblies and major piping.2.3.This task includes all work associated with removal/replacement of concrete and structural steel.Removal items include: Erection of scaffolding to remove piping and electrical components, cut/removal of the concrete shield wall above EL 58'nd the floor slab at EL 58', the concrete shield wall below EL 58', and removal of structural steel.Replacement items include: Installation of rebar and cadweld splices, erection of form work and shoring, concrete placement, and installation of structural steel.This task includes installation/removal of the pedestal crane foundations, assembly.and erection of cranes and the polar crane trolley,-and disassembly and removal of cranes and the polar crane trolley.Items included in this task are: Erection/removal'.of scaffolding from El 58'o'l 93', removal/installation of insulation and piping, upper'ssembly girth c'ut, cutting internal pipe and structural members inside the S/G, upper assembly modifications, and the upper assembly girth.weld.0.Construction of temporary facilities and support services.The major exposure items in this task are: Routing of welding leads, installation of temporary power for small tools and lighting in the area near the S/G (most will be inside the secondary shield wall between El 10'nd El 30'6"), and maintenance of temporary power and lighting for the entire outage.5.General decontamination and disposal of contaminated materials/cleanup.
Progress Report Number 0 will contain information from 30 March, 1983 through project completion (early May, 1983). This final report will also contain a summary for those tasks where the actual person-rem expended was significantly greater than the estimated values. This sumeKry will include a discussion of the lower expended exposure for the Unit 0 SGRP as compared to the Unit 3 SGRP and recommended changes in techniques and methods that should be evaluated to determine their effects on further reducing exposure for steam generator replacement - channel cut method.
5.This task includes general area decontamination of the containment prior to commencement of major work, continuous containment decontamination for the entire outage, and removal and~disposal of contaminated material for the entire outage.  
 
~~
I
~
  ~
TABLE 1 DESCRIPTION OF MA3OR TASKS TASK                                 TASK DESCRIPTION
: 1. Concrete and structural               This task includes all work associated steel removal and                      with removal/replacement of concrete placement.                            and structural steel. Removal items include: Erection of scaffolding to remove piping and electrical components, cut/removal of the concrete shield wall above EL 58'nd the floor slab at EL 58',
the concrete shield wall below EL 58', and removal of structural steel. Replacement items include: Installation of rebar and cadweld splices, erection of form work and shoring, concrete placement, and installation of structural steel.
    '2. Construction of pedestal          2. This task includes installation/removal of cranes, preparation of                the pedestal crane foundations, assembly .
polar crane, miscellaneous            and erection of cranes and the polar crane cribbing platforms, S/G                trolley,-and disassembly and removal of transfer bridge.                      cranes and the polar crane trolley.
    . 3. Removal, modification and        3. Items included in this task are: Erection/
reinstallation of S/G                  removal'.of scaffolding from El   58'o'l upper assemblies and                      93', removal/installation of insulation major piping.                          and piping, upper'ssembly girth c'ut, cutting internal pipe and structural members inside the S/G, upper assembly modifications, and the upper assembly girth. weld.
: 0. Construction of temporary             The major exposure items in this task are:
facilities and support                Routing of welding leads, installation of services.                              temporary power for small tools and lighting in the area near the S/G (most will be inside the secondary shield wall between El 10'nd El 30'6"), and maintenance of temporary power and lighting for the entire outage.
: 5. General decontamination and       5. This task includes general area disposal of contaminated              decontamination of the containment prior materials/cleanup.                    to commencement of major work, continuous containment decontamination for the entire outage, and removal and
                                              ~
disposal of contaminated material for the entire outage.
 
  ~
~
 
10 TABLE 1 (continued)
10 TABLE 1 (continued)
DESCRIPTION OF MA3OR TASKS TASK 6.Re'moval and reinstallation of miscellaneous piping, equipment and insulation.
DESCRIPTION OF MA3OR TASKS TASK                                   TASK DESCRIPTION
7.Non-manuals (e.g., QC, Engineers, HPs).S.Decontamination of the channel head.9.Cut channel head and remove old S/G lower assembly.10.SVeld shield cover on lower assembly;a.At channel head b.At transition end 11.Cut and remove old divider plate, weld new divider plate.6.7.9.10.TASK DESCRIPTION This task includes removal of insulation from the steam generator and main steam and feedwater piping, installation of insulation on the new steam generators, and removal/installation of miscellaneous items.The non-manual category includes health physics, quality control, and engineering personnel, visitors, and Bechtel personnel required for the entire outage.Included in this task are mechanical grit blast decontamination of the channel head, and installation of inflatable plugs in the reactor coolant piping.This task includes installation of tenting and temporary shielding, cutting the transition cone, and channel head, and, rigging and removal of the lower assembly to the containment equipment hatch.The only item in this task'is welding of steel plates at each end of the steam generator to provide shielding and to prevent leakage.The divider plate was detached from the tubesheet as part of Task 9.Removal and placement of the divider plate to the channel head is included in this task.12.Install new S/G, weld channel head.13.Placement of steam generator in storage.12.13.This task includes erection/removal of scaffolding, rigging and moving the new steam generator, installation/removal of hydroplugs, channel head welding and grinding, and removal of the inflatable plugs in the reactor coolant pipes.This task includes transporting of the S/G from the containment equipment hatch into the storage compound and construction of a roof once the S/G's are in the compound.
: 6. Re'moval and reinstallation       6. This task includes removal of insulation of miscellaneous piping,                from   the steam generator and main steam equipment and insulation.              and feedwater piping, installation of insulation on the new steam generators, and removal/installation of miscellaneous items.
: 7. Non-manuals (e.g., QC,            7. The non-manual category includes health Engineers, HPs).                        physics, quality control, and engineering personnel, visitors, and Bechtel personnel required for the entire outage.
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. SVeld  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.
 
11 TABLE 2 PERSONNEL EXPOSURE  
11 TABLE 2 PERSONNEL EXPOSURE  


==SUMMARY==
==SUMMARY==
-PER TASK REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 0 TASK DESCRIPTION LABOR EXPENDED IN-RADIATION FIELD PERSONNEL EXPOSUREa (PERSON-HOURS)(PERSON-REM)
- PER TASK REPORTING PERIOD     3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT     - UNIT 0 LABOR EXPENDED IN-RADIATION FIELD             PERSONNEL EXPOSUREa (PERSON-HOURS)                 (PERSON-REM)
ESTIMATED ACTUAL ESTIMATED ACTUAL 1.Concrete and structural steel removal and replacement.
TASK DESCRIPTION              ESTIMATED           ACTUAL     ESTIMATED ACTUAL
13,660" 21,872 88 69.26 2.Construction of pedestal cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.10)280 2,135 32 0.83 3.Removal, modification and reinstallation of steam generator upper assemblies and major piping.20,600 03,100 256 203.23 0.Construction of temporary facilities and support services 5..General decontamination and disposal of contaminated materials/cleanup.
: 1. Concrete and structural steel         13,660 21,872           88   69.26 removal and replacement.
19, 120-30, 1.60 j 02,310~00,310 215-'0.01 201 167.20 6.Removal and reinstallation of miscellaneous piping equipment and insulation.
: 2. Construction of pedestal               10)280            2,135            32    0.83 cranes, preparation of polar crane, miscellaneous cribbing platforms, and steam generator transfer bridge.
7.Non-manuals (e.g.QC, Engineers, Health Physics).8.Decontamination of the channelhead.
: 3. Removal, modification and             20,600            03,100          256    203.23 reinstallation of steam generator upper assemblies and major piping.
9.Cut channel head and remove old steam generator lower asse mbly.10.%'eld shield cover on lower assembly: a.at channel head b.at transition end 8,850 68,500 1,800 3,200 760 530 17,862 03,199 5,550 0,916 1,120 916 125 97.83 036 157.89 210 90.71 166 05.59 00 16.39 53 10.82 12 TABLE 2 (continued).PERSONNEL EXPOSURE  
: 0. Construction of temporary              19, 120      -    30, 1.60        215- '0.01 facilities and support services                   j 5.. General   decontamination and         02,310   ~
00,310           201   167.20 disposal of contaminated materials/cleanup.
: 6. Removal and reinstallation of           8,850          17,862          125    97.83 miscellaneous piping equipment and insulation.
: 7. Non-manuals (e.g. QC,                 68,500            03,199          036  157.89 Engineers, Health Physics).
: 8. Decontamination of the                   1,800            5,550          210    90.71 channelhead.
: 9. Cut channel head and remove             3,200            0,916          166    05.59 old steam generator lower asse mbly.
: 10. %'eld shield cover on lower assembly:
: a. at channel head                         760           1,120           00   16.39
: b. at transition end                        530              916          53   10.82
 
12 TABLE 2 (continued)
                      .PERSONNEL EXPOSURE  


==SUMMARY==
==SUMMARY==
-PER TASK RE'PORTING PERIOD 3 FEBRUARY 198.TO 30 MARCH 1983 TURKEY POINT-UNIT 0~TASK DESCRIPTION LABOR EXPENDED IN RADIATION FIELD PERSONNEL EXPOSUREa (PERSON-HOURS)(PERSON-REM)
PER TASK RE'PORTING PERIOD 3 FEBRUARY 198. TO 30 MARCH 1983 TURKEY POINT       UNIT 0 ~
ESTIMATED ACTUAL ESTIMATED ACTUAL 11.Cut and remove old divider plate, weld new divider plate.2,600 3,065 29 62.10 12.Install new steam generator weld channel head.11,000 36,881 200 237.60 13 Placement of steam generator in storage.225 200 25 6.10 TOTAL Estimated Range 207)595 251,302 2,080 1,204.00 1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.
LABOR EXPENDED IN RADIATION FIELD         PERSONNEL EXPOSUREa (PERSON-HOURS)               (PERSON-REM)
TABLE 3A  
TASK DESCRIPTION            ESTIMATED           ACTUAL ESTIMATED ACTUAL
: 11. Cut and remove old divider               2,600         3,065               29   62. 10 plate, weld new divider plate.
: 12. Install new steam generator             11,000       36,881             200   237.60 weld channel head.
13   Placement of steam generator               225           200             25     6.10 in storage.
TOTAL                                 207)595         251,302         2,080 1,204.00 Estimated Range                                                  1730-2080 a Actual exposures are estimated by self-reading pocket dosimeter totals.
 
TABLE 3A


==SUMMARY==
==SUMMARY==
OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED LABOR TO DATE EXPOSURE PERIOD" TO-DATE (PERSON-HOURS)(PERSON-NOURS)(PERSON"REM)(PERSON-REM)(PERSON"REM)
OF PREPARATORY       ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL                           ACTUAL EXPOSURE   ACTUAL EXPOSURE     ACTIVITY ESTIMATED       LABOR EXPENDED           ESTIMATED     FOR REPORTING       EXPENDED         STATUS
ACTIVITY STATUS (C-COMPLETE)(I-IN PROGRESS)l.Initial Containment Decontamination.
                                                                                                                    "      TO-DATE ACTIVITY DESCRIPTION                LABOR             TO DATE               EXPOSURE         PERIOD                       (C-COMPLETE)
4,816 2~Reactor Cavity Decontamination.
(PERSON-HOURS)     (PERSON-NOURS)         (PERSON"REM)     (PERSON-REM)     (PERSON"REM) (I-IN PROGRESS)
3,276 162 45.00 0.00 0.00 0.00 18.39 1.51.3.Reactor Cavity Liner Plate Inspection.
: l. Initial Containment   Decontamination.     4,816               3,276                 45.00             0.00           18.39 2~ Reactor Cavity Decontamination.                                    162                0.00             0.00             1.51
4.Install 8/C Transfer Bridge.960 300 147 0.00 1.21 0.00 0.00 6.04 0.29 5.Remove Emergency Containment Coolers.6.Remove CRDM Coolers and Fans.140 67 7.Rerate Polar Crane and Load Test.: 4,571 78 215[~i~.1,481 1.68 0.28 9.49 0.00 0.00 0.00 0.24 1.34 2.97 8.Disassemble Manipulator Crane and Store.9.Install Cherry Pickers.10.Remove Reactor Coolant Pump Motors.I 0 2,430 128 rent 4 266 397 0.00 6.06 0.00 0.00/0.00 0.00 0.91 1.35 2.59 C  
.3. Reactor Cavity Liner Plate Inspection.                           300                  0.00              0.00            6.04
: 4. Install 8/C Transfer Bridge.                 960                 147                 1.21             0.00             0.29
: 5. Remove Emergency   Containment Coolers.       140                  78                1.68              0.00            0.24
: 6. Remove CRDM   Coolers and Fans.                 67                 215                0.28              0.00            1.34
[    ~ i ~
: 7. Rerate Polar Crane and Load Test.     :     4,571             .
1,481                 9.49             0.00             2.97
: 8. Disassemble Manipulator Crane and Store.                                           0                128                0.00              0.00            0.91 rent 4                        /
: 9. Install Cherry Pickers.                   2,430                 266                 6.06             0.00             1.35
: 10. Remove  Reactor Coolant  Pump Motors.                             397                0.00             0.00             2.59             C I


TABLE 3A.(Continued)
TABLE   3A.(Continued)


==SUMMARY==
==SUMMARY==
OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARGE 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED LABOR TO DATE EXPOSURE PERIOD TO-DATE (PERSON-BOURS)(PERSON-HOURS)(PERSON-REM)(PERSON-REM)(PERSON-REM)
OF PREPARATORY       ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARGE 1983 TURKEY POINT       - UNIT 4 ACTUAL                           ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVITY ESTIMATED       LABOR EXPENDED             ESTIMATED   FOR REPORTING     EXPENDED         STATUS;.
ACTIVITY STATUS;.(C-COMPLETE)(I-IN PROGRESS)ll.Disconnect/Remove Permanent Electrical Equipment and Cables.12.Install Temporary Pover, Lighting and Electrical Items.13.Remove Miscellaneous Steel.430 1,148 580 304 4,458 3,532 1.93 49.50 6.21 0.00 0.00 0.00 0.79'18.55 8.20 C 14.Install/Maintain S/G Temporary Containments and Ventilation.
ACTIVITY DESCRIPTION              LABOR             TO DATE                 EXPOSURE         PERIOD         TO-DATE     (C-COMPLETE)
15.Install Temporary Shielding.
(PERSON-BOURS)     (PERSON-HOURS)           (PERSON-REM)     (PERSON-REM)   (PERSON-REM) (I-IN PROGRESS) ll. Disconnect/Remove Permanent Electrical Equipment and Cables.         430                304                  1.93            0.00          0.79
16.Install Scaffolding-all levels.1,008 120 1,440 5i203 3.31 11013 lt.63 tr~>r~1, 193 2.38 0.00 0.00 0.00 2.92 11.27 34.19 17.Cut and remove concrete 30'6 and 58'levation.
: 12. Install Temporary Pover, Lighting and Electrical Items.                   1,148              4,458                  49.50            0.00        '18.55
18.Project nonmanual support.19.On"going Decontamination Activities.
: 13. Remove Miscellaneous Steel.               580             3,532                   6.21             0.00           8.20             C
5,334 6g927 1,204 4,173 7~207 1,092 F 52.30 60.00 8.19 0.00 0 00 0.00 38.91 35.57 6.13 C TABLE 3A (Continued)
: 14. Install/Maintain   S/G Temporary Containments and   Ventilation.         1,008              11013                  lt.63            0.00          2.92 tr ~ > r ~
: 15. Install Temporary Shielding.               120            1, 193                  2.38            0.00          11.27
: 16. Install Scaffolding-all levels.         1,440             5i203                   3.31             0.00         34.19
: 17. Cut and remove concrete 30'6                                         F and 58'levation.                       5,334              4,173                  52.30            0.00          38.91
: 18. Project nonmanual support.               6g927              7~207                  60.00            0 00          35.57              C
: 19. On"going Decontamination Activities.                             1,204             1,092                   8.19             0.00           6.13
 
TABLE 3A (Continued)


==SUMMARY==
==SUMMARY==
OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED LABOR TO DATE EXPOSURE PERIOD TO-DATE (PERSON-HOURS)
OF PREPARATORY   ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL                     ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVIT ESTIMATED       LABOR EXPENDED     ESTIMATED     FOR REPORTINC     EXPENDED         STATUS ACTIVITY DESCRIPTION          LABOR             TO DATE         EXPOSURE         PERIOD         TO-DATE     (C-COMPLETE)
~(PERSON-HOURS)(PERSON-REM)(PERSON-REM)(PERSON-REM)
(PERSON-HOURS)   ~ (PERSON-HOURS)   (PERSON-REM)     (PERSON-REM)   (PERSON-REM) (I-IN PROGRESS)
ACTIVIT STATUS (C-COMPLETE)(I-IN PROGRESS)20.Containment Tool and Weld Rod Room Support.21.Remove/dispose of contaminated materials.
: 20. Containment Tool and Weld Rod Room Support.                   1,232                  506            7.55            0.00          Oo35
22.Crane operation/maintenance.
: 21. Remove/dispose of contaminated materials.                             900              3 g009            7.41            0.00          18.64            C  ~
23.Miscellaneous Activities.
: 22. Crane operation/maintenance.           685              3,722              1.36            0.00          7.63
Total-Phase I 1,232 900 685 1,000 34g992 506 3 g009 3,722 7,560 491412 7.55 7.41 1.36 , 1.51~E 283 0.00 0.00 0.00 0.00 0.00 Oo35 18.64 7.63 11.21 229.99 C~
: 23. Miscellaneous Activities.           1,000               7,560           , 1.51             0.00         11.21 Total  - Phase I                    34g992              491412
                                                                      ~      E 283            0.00         229.99


TABLE 3B  
TABLE 3B


==SUMMARY==
==SUMMARY==
OF REMOVAL ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACIUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIHATED FOR REPORTINC EXPENDED LABOR TO DATE EXPOSURE PERIOD TO-DATE (PERSON-HOURS)(PERSON-HOURS)(PERSON-REM)(PERSON-REH)(PERSON-REM)
OF REMOVAL   ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL                         ACTUAL EXPOSURE ACIUAL EXPOSURE     ACTIVITY ESTIMATED     LABOR EXPENDED         ESTIHATED     FOR REPORTINC     EXPENDED           STATUS ACTIVITY DESCRIPTION                  LABOR           TO DATE             EXPOSURE         PERIOD       TO-DATE       (C-COMPLETE)
ACTIVITY STATUS (C-COMPLETE)(I-IN PROGRESS)1.Remove insulation from Aq Bq&C S/G's.2.Remove feedvater piping A, B,&C S/G's.3.Remove main steam piping A, B~&C S/G's.3)500 147 125 6~721 2,932 331 77'00 1.50 0.61 0.00 0.00 0.00 63.64 10.76 1.76 4.Remove miscellaneous piping from A, B,&C S/G cubicles.1,410 1 g'370,,$17.62 0.00 18.11 C 5.Conduct channel head decontamination A, B~&C S/C's.lg835 5,547" 214.00 0.00 90.71 6.Cut A, B,&0 S/C upper assemblies.
(PERSON-HOURS)   (PERSON-HOURS)       (PERSON-REM)     (PERSON-REH) (PERSON-REM)   (I-IN PROGRESS)
630 683 33.30 0.00/2'8 7.Lift A, B,&C S/C upper assemblies, invert and place in racks.525 I 1 g 575 6.75 0.00 7.74 C 8.Cut A, B,&C S/G channel heads.9.Install tube bundle shield covers A, B,&C 8/C's.714 525 2,il5 916 60.24 53.00 0.00 0.00 22.33 14.82 TABLE 38 (Continued)
: 1. Remove insulation from Aq Bq & C S/G's.                             3)500              6~721                77'00            0.00        63.64
SUMHARY OF REMOVAL ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED LABOR TO DATE EXPOSURE PERIOD'O-DATE (PERSON-HOURS)(PERSON-HOURS)(PERSON"REM)(PERSON"REH)(PERSON-REH)
: 2. Remove feedvater piping A, B, & C S/G's.                             147              2,932                1.50            0.00        10.76
ACTIVITY STATUS;.(C-COHPLETE)(I-IN PROGRESS)10.Cut A, B&C S/G divider plates.ll.Lift A, B&C SCLA, cut and remove seismic rings.12.Install tube sheet shield covers A, B&C S/G's.13.Remove A, B&C SGLA's from reactor containment building and place in.storage compound.14..Maintain temporary power, lighting&electrical items.15'aintain, erect, and remove scaffolding.
: 3. Remove main steam     piping A, B~ & C   S/G's.                             125                 331               0.61           0.00         1.76
16.On going decontamination activities.
: 4. Remove miscellaneous     piping from A, B,   & C S/G cubicles.           1,410             1 g'370,,         $ 17.62           0.00         18.11               C
17.Remove/dispose of contaminated materials'52 Ig089 755 225 2, 100 840 10,900 3~600 317 221 1,124 200'''i793 7,308 2,540 7,617 77.16 40.00 ZS.OO 55+00 8.40 32.76 29'2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.64 3.59 16.39 6.14 5.93 31.47 12.74 37.65  
: 5. Conduct channel head decontamination A, B~ & C S/C's.
~~TABLE 3B (Continued)
lg835             5,547             214.00             0.00         90.71
: 6. Cut A, B,   & 0 S/C upper assemblies.                                     630                 683             33.30     /      0.00         2 '8
: 7. Lift A, B,   & C S/C upper assemblies, I invert   and place in racks. 525             1 g 575               6.75           0.00         7.74               C
: 8. Cut A, B,   & C   S/G channel heads.           714            2,il5                60.24            0.00        22.33
: 9. Install tube bundle shield covers A, B, & C 8/C's.                         525                 916             53.00           0.00         14.82
 
TABLE 38 (Continued)
SUMHARY OF REMOVAL ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT     - UNIT 4 ACTUAL                       ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVITY ESTIMATED     LABOR EXPENDED         ESTIMATED   FOR REPORTINC       EXPENDED         STATUS;.
ACTIVITY DESCRIPTION              LABOR           TO DATE             EXPOSURE       PERIOD     'O-DATE           (C-COHPLETE)
(PERSON-HOURS)   (PERSON-HOURS)       (PERSON"REM)   (PERSON"REH)     (PERSON-REH) (I-IN PROGRESS)
: 10. Cut A, B & C S/G divider plates.                           317                                0.00            3.64 ll. Lift A, B   & C SCLA,   cut and remove seismic   rings.                 Ig089              221                77.16          0.00            3.59
: 12. Install tube sheet shield covers A, B & C S/G's.                       755            1,124                40.00          0.00            16.39
: 13. Remove A, B & C SGLA's from reactor containment building and place in. storage compound.              225              200''              ZS.OO          0.00            6.14 14.. Maintain temporary power, lighting & electrical items.                                       'i793 2, 100                                55+00          0.00            5.93 15 'aintain,     erect,   and remove scaffolding.                                 840            7,308                8.40          0.00            31.47
: 16. On activities. materials'52 going decontamination 10,900            2,540                32.76          0.00            12.74
: 17. Remove/dispose   of contaminated                             3~600             7,617               29 '2           0.00           37.65
 
                                                                                                                                    ~ ~
TABLE 3B   (Continued)


==SUMMARY==
==SUMMARY==
OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED LABOR TO DATE EXPOSURE PERIOD TO-DATE (PERSON-HOURS)(PERSON-HOURS)(PERSON REM)(PERSON"REM)(PERSON-REM)
OF REMOVAL   ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL                       ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVITY ESTIMATED     LABOR EXPENDED       ESTIMATED     FOR REPORTINC     EXPENDED         STATUS ACTIVITY DESCRIPTION      LABOR           TO DATE           EXPOSURE         PERIOD         TO-DATE     (C-COMPLRTE)
ACTIVITY STATUS (C-COMPLRTE)(I-IN PROGRESS)18.Project non~anual support.19.Containment tool and weld rod room support.20.Crane operation and maintenance.
(PERSON-HOURS)   (PERSON-HOURS)     (PERSON REM)     (PERSON"REM)   (PERSON-REM) (I-IN PROGRESS)
27,725 840 3,015 6,410 39 2,334 214.72 2.52 5.44 Q.OQ 0.00 0.00 24 58 0.09 4.05 21.Miscellaneous Activities.
: 18. Project non~anual support.       27,725            6,410            214.72              Q.OQ          24 58
Total-Phase II 8g377, 1,364 69,129 54,4'67'P 58.00 1 1,016 0.00 0.00 16.60 395.62 tent 4  
: 19. Containment tool and weld rod room support.                   840                39            2.52            0.00            0.09
*TABLE 3C  
: 20. Crane operation and maintenance.                     3,015             2,334               5.44             0.00           4.05
: 21. Miscellaneous Activities.       8g377,           1,364             58.00            0.00          16.60 Total  - Phase II                69,129           54,4'67'         1 1,016             0.00         395.62 P
tent 4
 
TABLE 3C


==SUMMARY==
==SUMMARY==
OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED LABOR TO DATE EXPOSURE PERIOD TO-DATE (PERSON-HOURS)(PERSON-HOURS)(PERSON"REM)(PERSON"REM)(PERSON-REM)
OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT   - UNIT 4 ACTUAL                       ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVITY ESTIMATED       LABOR EXPENDED         ESTIMATED   FOR REPORTING     EXPENDED         STATUS ACTIVITY DESCRIPTION                  LABOR             TO DATE             EXPOSURE       PERIOD         TO-DATE     (C-COMPLETE)
ACTIVITY STATUS (C-COMPLETE)(I-IN PROGRESS)1.Remove S/G upper assembly internals~and install/modify A, B and C S/G secondary internal components..
(PERSON-HOURS)     (PERSON-HOURS)       (PERSON"REM)   (PERSON"REM)   (PERSON-REM) (I-IN PROGRESS)
2.Weld preparation of A~B&C S/G channel head remnants.3.Install/weld A, B&C SGLA's (includes post-weld heat treatment).
: 1. Remove S/G upper assembly internals
11,260 840 8)696 6~286 1,757 27,143 93.10 7.71 191.64 0.00 0.00 105.80 14.01 12.69 213.77 C C 4~Install/weld A, B&C S/G divider plates.lp554 2,764 15i10 58 46 58.46 5;Install/weld A, B&C S/C upper assemblies.
~ and install/modify A, B and C S/G secondary internal components..         11,260              6~286              93.10          0.00          14.01              C
6.Installation of A, B&C S/G main steam piping.7, Installation of A, B&C S/G feedwater piping.8, Install insulation A, B&C S/G's.9.Maintain temporary power, lighting and electrical items.6,280 1,250 lp680 3,486 2g850 8,432 996 1,013 2,435 7,819 23.82 5.50 6.80 29 40 65.00~~4.68 0.80 1.23 4.17.8-03 13.60 2.28 lo89 4.17 19.14 TABLE 3C (Continued)
: 2. Weld preparation of   A~ B & C S/G channel head remnants.                         840              1,757                  7.71        0.00          12.69
SUIRY OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT-UNIT 4 1 1 I-1 1 (1 I ACTIVITY DESCRIPTION ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS LABOR TO DATE EXPOSURE PERIOD'O-DATE (C-COMPLETE)(PERSON-HOURS)(PERSON"HOURS)(PERSON-REM)(PERSON"REM)(PERSON-REM)(I-IN PROGRESS)10.Maintain/erect/remove scaffolding.
: 3. Install/weld   A, B & C SGLA's (includes post-weld heat treatment).         8) 696             27,143             191.64         105.80         213.77             C 4~ Install/weld A,   B & C S/G divider plates.                             lp554               2,764               15i10         58 46           58.46 5; Install/weld A, B   & C S/C upper assemblies.                           6,280              8,432              23.82          4.68          13.60
2,840 11.On-going decontamination activities.
: 6. Installation of   A, B & C S/G main steam piping.                         1,250                  996                  5.50        0.80            2.28 7, Installation of   A, B & C S/G feedwater piping.                           lp680                1,013                  6.80        1.23            lo89 8, Install insulation   A, B & C   S/G's.     3,486              2,435              29 40          4.17.          4.17
10,920 171625-20.67 5,096.32.76 35.16 7.36 58.58~14.41 12.Remove/dispose of contaminated materials'.
: 9. Maintain temporary power, lighting and electrical items.                       2g850               7,819             65.00           8-03           19.14
13.Project non~anual support.3,600 14,460 14,931 251448 29.62 86.27 33.54 44.40 54.16 74.37 C~14.Containment Tool&Meld rod room support.15.Crane operation/maintenance.
                                                                                        ~ ~
16.Miscellaneous activities.
 
8,704 5,044 840 458 n 21740 5,296 1 2~52 0.49 5.43 2 33, 28'6.4.67 0.84 4.11 16.12~1 tJ Q~Total Phase III 82,000 132,539 644 311.12 562.60}}
1 1
I-1 1
TABLE 3C (Continued)                                                               (
SUIRY OF INSTALLATION ACTIVITY EXPOSURES                                                   1 REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983                                                 I TURKEY POINT UNIT 4 ACTUAL                     ACTUAL EXPOSURE ACTUAL EXPOSURE     ACTIVITY ESTIMATED     LABOR EXPENDED     ESTIMATED     FOR REPORTING     EXPENDED         STATUS ACTIVITY DESCRIPTION                LABOR           TO DATE         EXPOSURE           PERIOD   'O-DATE           (C-COMPLETE)
(PERSON-HOURS)   (PERSON"HOURS)   (PERSON-REM)     (PERSON"REM)   (PERSON-REM) (I-IN PROGRESS)
: 10. Maintain/erect/remove scaffolding.           2,840           171625    -        20.67            35.16          58.58
: 11. On-going decontamination   activities. 10,920             5,096   .       32.76             7.36       ~ 14.41
: 12. Remove/dispose   of contaminated materials'.                     3,600            14,931            29.62            33.54          54.16            C  ~
: 13. Project non~anual support.                 14,460           251448             86.27           44.40           74.37
: 14. Containment Tool   & Meld                                                     1 1
rod room support.                               840              458              2 ~ 52          0.49            0.84                    tJ n                                                                        Q      ~
: 15. Crane operation/maintenance.                 21740            5,296              5.43            2 33,          4.11
: 16. Miscellaneous   activities.                 8,704             5,044             28 '6   .       4.67           16.12~
Total Phase III                           82,000           132,539               644         311.12         562.60}}

Latest revision as of 23:26, 3 February 2020

Forwards Third Radiological Progress Rept for Steam Generator Repair Program
ML17345B061
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 04/29/1983
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML17345B062 List:
References
L-82-272, NUDOCS 8305030168
Download: ML17345B061 (32)
v • d • e


Text

I i

'REGULATOR NFORMATION DISTRIBUTION 'S EM ('RIDS)

'ACCESSION,NBRt8305030166 DOC DATEt 83/04/29 NOTARIZED: NO DOCKET ¹

'FAGIL;.50 '251 tTur key Po'fnt 1Pl anti ',Uni;t 0i Florida IPower -and Light "C 05000251

'AUTH ~ NAME AUTHOR 'AFFILIATION

'UHRIGiR,E,:F 1 or ida iPower I Light Co, GREC IP ~ NAME REC IP IENT. 'AF F IL'IATION VARGAP'S,AB Operating Reactons Branch 1 1

SUBJECT:

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.EXTERNALs ACRS =09 l6 I 6 LPDR 03

'NRC:PDR *02'. 1 1 NSIC 05 NT I' 1 1

)TOTAL, NUMBER, OF'."COPIES'EQUIRED: LTTR 25 ENCL 23

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O. BOX 14000, JUNO BEACH, FL 33408

'sg FLORIDA POWER 5 LIGHT COMPANY April 29, 1983 L-83-272 Office of Nuclear Reactor Regulation Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch gl Division of Licensing U. S. Nuclear Regulat'ory Commission Washington, D.C. 20555

Dear Mr . Varga:

I Re: Turkey Point Unit 4 Docket No. 50-251 Steam Generator Repair Program

- Radiolo ical Pro ress Re ort - No. 3 Please find attached our thi"rd Radiological Progress Report for the Steam Generator Repair Program as required by Section 3.H.(2)(c) of DPR-41.

Very truly yours, Robert E. Uhrig President 'ice Advanced Systems & Technology REU/PLP/cab Attachment cc: J. P. O'Reilly, Region II Harold F. Reis, Esquire 8305030ih8 8S0yg9 PDR IIIIDOCK R

0500025i PDR.. ~ ...

PEOPL'E... SERVING PEOPLE

0 I TABLE OF CONTENTS PAGE NO.

1.0 'NTRODUCTION 2.0 OCCUPATIONAL RADIATIONEXPOSURE 2.1 General 2.2 Description and Format of Exposure Data 2 2.3 Discussion of Exposure Results 3 3.0 APPLICATION OF DOSE REDUCTION TECHNIQUES (ALARA PRINCIPLES) 3.1 General 3.2 Contamination Control Envelopes and Ventilation 3.3 Installation of Steam Generator Lower Assemblies(SGLAs) 3.0 Welding of Steam Generator Divider Plates 3.5 Reactor Head Preparation for Hot Functional Testing 5 3.6 General Techniques and Practices 5 0.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 0.1 General 0.2 Liquid Releases 6 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 16 TABLE 3C Summary of Installation Activity Exposures 19 TABLE 3D Summary of Post-Installation Activity Exposures 21 TABLE 0 Personnel Exposure Summary - Per Phase 20 TABLE 5 Summary, of Radioactive Effluent Releases 25 TABLE 6 Summary of Solid Low Level Radioactive Waste Shipments 28

1.0 INTRODUCTION

Radiological Progress Report No. 3 contains information pertaining to the radiological aspects of the Unit 0 Steam Generator Repair Program (SGRP) for the period February 3, 1983 through March 30, 1983. This information includes the following:

a. An assessment and summary of the occupational exposure and labor expended for each reporting period (throughout the project).
b. An evaluation of the effectiveness of dose reduction techniques (ALARA principles). F
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. Removal of steam generator transfer bridge.
2. Installation of main steam and feedwatez piping.
3. Complete installation of steam generator upper and lower assemblies.

Welding of steam generator divider plates.

5.

/

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

l

6. Installation of insulation on steam genet ators.
7. Installation of miscellaneous piping in,steam generator cubicles.
8. Installation of miscellaneous steel.
9. Installation of reactor coolant pump motors.
10. Installation of emergency containment coo'lers, control rod drive mechanism coolers and fans.
11. Installation of concrete stop logs, concrete forms, rebar and pouring of new concrete.
12. Preparation for and conducting of hot functional testing.
13. Cleanup activities (removal of scaffolding and support equipment, removal of temporary shielding).

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

I 2.0 OCCUPATIONAL RADIATIONEXPOSURE 2.1 General As indicated in Radiological Progress Report No. 1, occupational exposure to radiation may'e considered the major radiological impact of the SGRP. The program developed to collect exposure information and provide accurate "

assessments of tasks performed is discussed in detail in Section 2.1 2.3 of Radiological Progress Report No. 1. This program was utilized throughout this reporting period. -A description of the thirteen (13) major tas' r ~

15. Install Temporary Shielding. 120 1, 193 2.38 0.00 11.27
16. Install Scaffolding-all levels. 1,440 5i203 3.31 0.00 34.19
17. Cut and remove concrete 30'6 F and 58'levation. 5,334 4,173 52.30 0.00 38.91
18. Project nonmanual support. 6g927 7~207 60.00 0 00 35.57 C
19. On"going Decontamination Activities. 1,204 1,092 8.19 0.00 6.13

TABLE 3A (Continued)

SUMMARY

OF PREPARATORY ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVIT ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC 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)

20. Containment Tool and Weld Rod Room Support. 1,232 506 7.55 0.00 Oo35
21. Remove/dispose of contaminated materials. 900 3 g009 7.41 0.00 18.64 C ~
22. Crane operation/maintenance. 685 3,722 1.36 0.00 7.63
23. Miscellaneous Activities. 1,000 7,560 , 1.51 0.00 11.21 Total - Phase I 34g992 491412

~ E 283 0.00 229.99

TABLE 3B

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACIUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIHATED FOR REPORTINC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

1. Remove insulation from Aq Bq & C S/G's. 3)500 6~721 77'00 0.00 63.64
2. Remove feedvater piping A, B, & C S/G's. 147 2,932 1.50 0.00 10.76
3. Remove main steam piping A, B~ & C S/G's. 125 331 0.61 0.00 1.76
4. Remove miscellaneous piping from A, B, & C S/G cubicles. 1,410 1 g'370,, $ 17.62 0.00 18.11 C
5. Conduct channel head decontamination A, B~ & C S/C's.

lg835 5,547 214.00 0.00 90.71

6. Cut A, B, & 0 S/C upper assemblies. 630 683 33.30 / 0.00 2 '8
7. Lift A, B, & C S/C upper assemblies, I invert and place in racks. 525 1 g 575 6.75 0.00 7.74 C
8. Cut A, B, & C S/G channel heads. 714 2,il5 60.24 0.00 22.33
9. Install tube bundle shield covers A, B, & C 8/C's. 525 916 53.00 0.00 14.82

TABLE 38 (Continued)

SUMHARY OF REMOVAL ACTIVITY EXPOSURES REPORTINC PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED STATUS;.

ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD 'O-DATE (C-COHPLETE)

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

10. Cut A, B & C S/G divider plates. 317 0.00 3.64 ll. Lift A, B & C SCLA, cut and remove seismic rings. Ig089 221 77.16 0.00 3.59
12. Install tube sheet shield covers A, B & C S/G's. 755 1,124 40.00 0.00 16.39
13. Remove A, B & C SGLA's from reactor containment building and place in. storage compound. 225 200 ZS.OO 0.00 6.14 14.. Maintain temporary power, lighting & electrical items. 'i793 2, 100 55+00 0.00 5.93 15 'aintain, erect, and remove scaffolding. 840 7,308 8.40 0.00 31.47
16. On activities. materials'52 going decontamination 10,900 2,540 32.76 0.00 12.74
17. Remove/dispose of contaminated 3~600 7,617 29 '2 0.00 37.65

~ ~

TABLE 3B (Continued)

SUMMARY

OF REMOVAL ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTINC EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLRTE)

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

18. Project non~anual support. 27,725 6,410 214.72 Q.OQ 24 58
19. Containment tool and weld rod room support. 840 39 2.52 0.00 0.09
20. Crane operation and maintenance. 3,015 2,334 5.44 0.00 4.05
21. Miscellaneous Activities. 8g377, 1,364 58.00 0.00 16.60 Total - Phase II 69,129 54,4'67' 1 1,016 0.00 395.62 P

tent 4

TABLE 3C

SUMMARY

OF INSTALLATION ACTIVITY EXPOSURES REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 TURKEY POINT - UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD TO-DATE (C-COMPLETE)

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

1. Remove S/G upper assembly internals

~ and install/modify A, B and C S/G secondary internal components.. 11,260 6~286 93.10 0.00 14.01 C

2. Weld preparation of A~ B & C S/G channel head remnants. 840 1,757 7.71 0.00 12.69
3. Install/weld A, B & C SGLA's (includes post-weld heat treatment). 8) 696 27,143 191.64 105.80 213.77 C 4~ Install/weld A, B & C S/G divider plates. lp554 2,764 15i10 58 46 58.46 5; Install/weld A, B & C S/C upper assemblies. 6,280 8,432 23.82 4.68 13.60
6. Installation of A, B & C S/G main steam piping. 1,250 996 5.50 0.80 2.28 7, Installation of A, B & C S/G feedwater piping. lp680 1,013 6.80 1.23 lo89 8, Install insulation A, B & C S/G's. 3,486 2,435 29 40 4.17. 4.17
9. Maintain temporary power, lighting and electrical items. 2g850 7,819 65.00 8-03 19.14

~ ~

1 1

I-1 1

TABLE 3C (Continued) (

SUIRY OF INSTALLATION ACTIVITY EXPOSURES 1 REPORTING PERIOD 3 FEBRUARY 1983 TO 30 MARCH 1983 I TURKEY POINT UNIT 4 ACTUAL ACTUAL EXPOSURE ACTUAL EXPOSURE ACTIVITY ESTIMATED LABOR EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS ACTIVITY DESCRIPTION LABOR TO DATE EXPOSURE PERIOD 'O-DATE (C-COMPLETE)

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

10. Maintain/erect/remove scaffolding. 2,840 171625 - 20.67 35.16 58.58
11. On-going decontamination activities. 10,920 5,096 . 32.76 7.36 ~ 14.41
12. Remove/dispose of contaminated materials'. 3,600 14,931 29.62 33.54 54.16 C ~
13. Project non~anual support. 14,460 251448 86.27 44.40 74.37
14. Containment Tool & Meld 1 1

rod room support. 840 458 2 ~ 52 0.49 0.84 tJ n Q ~

15. Crane operation/maintenance. 21740 5,296 5.43 2 33, 4.11
16. Miscellaneous activities. 8,704 5,044 28 '6 . 4.67 16.12~

Total Phase III 82,000 132,539 644 311.12 562.60

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