ML18139A872
| ML18139A872 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/01/1980 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A871 | List: |
| References | |
| NUDOCS 8012040308 | |
| Download: ML18139A872 (31) | |
Text
e e
STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 1 RADIOLOGICAL PROGRESS REPORT - NO. 1 FOR THE PERIOD SEPTEMBER 14, 1980 THROUGH OCTOBER 31, 1980
.-8012040 DOCKET NO. 50-280 LICENSE NO. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY
TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General 2.2 Evaluation of Exposure Data 2.3 Description and Format of Exposure Data 2.4 Conclusions and Observations
. 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General 3.2 Containment Cleanup and Decontamination 3.3 Temporary Shielding 3.4 Steam Generator Water Level 3.5 Plasma-Arc Cutting Equipment 3.6 Temporary Containments and Ventilation 3.7 General Techniques and Practices 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General 4.2 Airborne Releases 4.3 Liquid Releases
- 4. 4 Solid Rad.ioacti ve Waste TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents PAGE NO.
PRl-1 PRl-2 PRl-2 PRl-2 PRl-3 PRl-4 PRl-5 PRl-5 PRl-5 PRl-5 PRl-7 PRl-8 PRl-9 PRl-10 PRl-12 PRl-12 PRl-12 PRl-12 PRl-12
e
1.0 INTRODUCTION
PRl-1 SSGP The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 1 commenced on September 14, 1980.
This initial progress report for the Unit No. 1 SGRP contains information on the radiolo-gical effects of the repair effort, and describes the measures taken to maintain these effects "as low as reasonably acheivable" (ALARA), during the period September 14 through October 31, 1980.
With regard to radiologicaJ_ effects, the major tasks accomplished during the reporting period involved shutdown and preparatory activities.
These included:
de fueling, initial containment cleanup and decontamination, installation of temporary shielding, and erection of scaffolding.
Several of the major removal activi-ties which were commenced during the reporting period also contri-buted significantly to the radiological effects assessed in this report.
Included are:
removal of insulation from the steam generators and associated primary and secondary piping, removal of miscellaneous
- piping, cutting of reactor coolant piping and disassembly of steam generator supports.
The report sections which follow provide an assessment of the occupational exposure
- expended, the dose reduction techniques employed and their effectiveness, and the radioactive effluents and solid waste generated during the reporting period.
Throughout this progress report and those to follow for the Unit No. 1 SGRP, reference will be made wherever appropriate to the progress reports issued during the Surry, Unit No. 2 SGRP for purposes of compari-
- son, and to identify differences in the replacement activities which have a significant effect on the radiological impact of the program.
2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General PRl-2 SSGP Occupational exposure to radiation is considered to be
- the major radiological effect of the SGRP.
As such, this aspect of the pro-ject underwent an extensive evaluation during the planning phase to provide realistic estimates of the amounts of personnel radiation exposure (manrem) which would be required to perform each of the tasks involved.
These estimates were based µpon the anticipated labor requirements (manhours) and the average radiation dose rates in the work area, and were presented in summary form in Table 5.3-1 of the report entitled "Steam Gen.erator Repair Program", dated August 17, 1977 and amendments thereto, hereafter referred to as the SGRP Report.
Prior to commencement of the project, a program was established to assess the actual exposures received by personnel during the repair effort.
This program was designed to provide data compatible with the detail and format of the exposure summary presented in Table
- 5. 3-1 of the SGRP Report, thereby permitting valid comparisons between estimated and actual expenditures.
2.2 Evaluation of Exposure Data The exposure assessment program referred to above is basically designed to utilize daily worker exposure data, as recorded by self-reading pocket dosimeters, in conjunction with contractor supplied, worker task data to determine task-related manrem expen-ditures.
The worker task data is standardized to a system of discrete work packages (called Engineering Task Assignments) which was developed during the project planning pha~e.
The use of this system to categorize exposure related work for individuals on a daily basis facilitates the process of compiling an accurate break-down of the collective exposure expended on the many tasks involved.
2.3 Description and Format of Exposure Data PRl-3 SSGP Table 1 presents a summary of the occupational radiation exposure expended during the reporting period, the labor and exposure ex-penditures to-date (i.e. from project commencement on September 14, 1980 to October 31, 1980), and the original estimated expenditures.
The following comments are provided for clarification and should be considered when reviewing the data presented.
(a) Additional tasks performed during the repair effort which were not listed in Table 5.3-1 of the SGRP report have been includ-ed in Table 1.
Similarily, exposures received by personnel performing functions not directly attributabie to any one task have been listed separately.
(b)
The "Task Status" indications listed in Table 1 are intended to aid in the process of comparing estimated vs. actual manrem expenditures during the repair effort. For tasks indicated as "in progress", significant exposure related work may remain to be performed and a realistic comparison may be impractical.
For "completed" tasks, the manrem and manhour values listed in Table 1 can be considered to represent the major significant expenditures for those tasks, therefore valid comparisons are possible. It should be recognized, however, that factors such as field changes to-procedures, dismantling of task related support equipment, localized work area cleanup, etc. may con-tinue to contribute small amounts of additional exposure and labor to a task for some time after completion is indicated.
(c)
The Phase Subtotals listed in Table 1 are calculated* by a summation of values for completed tasks.
Expenditures report-ed for "Additional Tasks" and "Unassigned Personnel Cate-gories" are allocated to a particular phase based upon the major activities being performed at the time they are incurred.
Thus, the Phase Subtotals also include these values for phases in which a majority of the tasks have been complet-ed.-
This is the case for Phase I (Shutdown and Preparatory Activities).
For Phases II through IV, The Phase Subtotals do not yet include the expenditures mentioned above since a major-ity of the tasks have yet to be commenced and/ or completed.
e 2:4 Conclusions and Observations PRI-4 SSGP As of the end of the reporting period, the SGRP for Unit No. 1 has been in progress for approximately*seven weeks.
Due to this fact, an evaluation of the data presented in Table 1 to identify evidence of developing trends with respect to occ*upational exposures is felt to be premature.
Should such trends develop as the repair effort for Unit No. 1 progresses, subsequent reports will describe them and attempt to determine the causes or contributing factors.
Additionally, when comparisons of total manrem expenditures requir-ed to complete important tasks identify significant differences I
between the SGRP for Units 1 and 2*, the reports will note these differences and describe the possible factors involved.
e 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General e
PRl-5 SSGP This section summarizes the specific techniques and practices which were employed during the initial reporting period in order to main-tain occupational exposures to radiation "as low as reasonably ach-ievable" (ALARA).
Where the available data permits, the following evaluations include a quantitative assessment of the manrem savings which can be attributed to the technique used.
Additional infor-mation on these techniques and how they relate to the overall steam generator replacement activities can be found in the SGRP Report.
- 3. 2 c*ontainment Cleanup and Decontamination After shutdown and the removal of all fuel from the reactor, a general cleaning of the containment interior was performed to remove loose radioactive contamination in the work areas and there-by reduce the potential for airborne contamination during subsequent activities.
Where appropriate, removable floor covering (plastic sheeting) has been applied to facilitate additional cleanup during the repair activities.
A special work crew has been retained to continuously clean the work areas and to perform equipment deconta-mination.
This effort will maintain optimum radiological working conditions and avoid buildups of debris.
While it is not possible to quantify the exposure savings attri-butable to this technique, the benefit of maintaining effective control of contamination is seen in terms of its contribution to minimizing the overall hazard associated with the SGRP.
3.3 Temporary Shielding The use of temporary shielding resulted in significant reductions in personnel radiation exposure during the SGRP for Unit No. 2.
A separate work package was devoted to the design and installation of this shielding, with particular emphasis placed on the lower steam generator cubicles where radiation levels are highest and several major removal and installation activities are performed.
While the temporary shielding applied to these areas in Unit No. 2 was suc-cessful in minimizing exposure rates for subsequent activities, the
e PRl-E SSGP task of installing the shielding required a significant amount of exposure (approximately 143 manrem).
In Unit No. 1, the benefit of this previous experience and the use of personnel with specific expertise in the installation of lead shielding has resulted in a considerable reduction in the time and exposure incurred for this task.
As seen in Table 1, the shielding performed during the reporting period required the expenditure of about 45 manrem.
Additional shielding will be installed during the removal and installation phases; however, the major portion of this task with respect to its exposure "cost" has been completed.
Detailed rad-iation surveys, performed prior to and after the installation of temporary shielding, have been used to assess the effectiveness of this technique in providing net reductions in personnel exposure for two of the major removal activities commenced during the reporting period.
(a)
The removal of miscellaneous piping located in the lower steam generator cubicles accounted for the expenditure of approxi-mately 10 manrem during the period.
Lead shielding applied directly to this piping and sheet lead "curtains" used to lower the general area radiation levels typically reduced average exposure rates of 800-1200 mR/hour to approximately 200 mR/hour for the removal task.
Thus, a reduction factor of about 5 was achieved, and results in a calculated exposure savings of 40 manrem.
(b)
The cutting and removal of reactor coolant piping has resulted in the expenditure of about 46 manrem to-date.
Prior to the installation of lead shielding on this pipe, contact exposure rates in the cut areas were 1200 mR/hour on the average.
The application of shielding reduced these rates to an average reading of 200 mR/hour.
This represents a reduction factor of
- 6.
The exposure savings attributed to shielding for this activity thus total about 230 manrem to-date.
e PRl-7 SSGP The assessments described above represent only a preliminary evaluation of the overall benefits expected to result from the application of temporary shielding techniques during the SGRP.
A major portion of the removal and installation activities have yet to be performed, and will benefit significantly from the shielding already in place as well as the additional applications planned.
Subsequent progress reports will provide further assessments of the "benefits and costs" of this ALARA technique.
3.4 Steam Generator Water Level Until the lower portion of the steam. generator is ready to be removed from the containment, the water level on the secondary side is maintained at a level covering the tube bundle.
The shielding effect provided by this water has historically resulted in an approximate 10 to 1 reduction of exposure levels for the areas of the steam generator above the channel head (Ref. SGRP Report, pages 9.A. 3-2 and 9.A. 3-3).
This reduction factor was confirmed during the Unit No. 2 SGRP by actual survey results.
For Unit No.
1, several tasks performed on or near the upper portion of the steam generators will benefit from the high water level.
These include:
(a)
Removal of Insulation (upper shell, mainsteam and feedwater piping),
(b)
Cut and Remove Steam Generator Upper Shell, (c) Cutting of Mainsteam and Feedwater Piping, and (d)
Removal of Steam Generato.r Level Instrumentation and Blowdown Piping.
While all of the tasks above were commenced during the reporting period, an assessment of the exposure savings attributable to steam generator water level will not be attempted until the generators are drained and surveys can be performed to determine the actual reductions achieved in Unit No. 1.
e 3.5 Plasma-Arc Cutting Equipment PRl-8 SSGP In order to remove the steam generator lower shell from the con-tainment, sections of the reactor coolant piping must be removed.
A plasma-arc cutting torch was chosen as the means,for performing these cuts.
Plasma-arc has high cutting speed and produces good cut quality for subsequent pipe stub-end refurbishment.
The high cutting rate was a primary factor in this choice since faster cutting means reduced exposure times.
During the evaluation of t~is task, alternate methods such as mechanical cutting and other flame cutting techniques were considered.
These alternatives were estimated to require 1 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per cut, as compared to 15 to 20 minutes for plasma-arc.
In actuality during the Unit No.
2 SGRP, the majority of the reactor coolant pipe cuts required approximately 20 minutes with the plasma-arc torch.
Similar performance has been observed in Unit No. 1; however, two improvements in the task of removing the reactor coolant pipe
- were made based on the Unit 2 experience.
First, studies conducted after the Unit 2 SGRP indicated that the number of coolant pipe sections required to be removed in order to achieve a proper subsequent fit-up to the new steam generators could be reduced in Unit 1, if the existing pipe alignment fell within desired tolerances.
Measurements taken in Unit 1 after the coolant pipe insulation was removed confirmed the desired existing alignment, and thus, only two pipe sections per generator have been removed instead of three as in Unit 2.
This meant that one less cut per generator was possible.
Second, the actual cutting process in Unit 2 required the plasma-arc torch to be manually propelled around a portion of its track.
For Unit 1, improvements in the track system allowed the torch to be self-propelled around the entire pipe girth, thereby eliminating the need for an individual to be in close proximity with the coolant pipe during the cutting process.
The two changes described above represent additional improvements to an already proven ALARA technique by further reducing the times spent in radiation areas.
e 3.6 Temporary Containments and Ventilation PRl-9 SSGP To a large degree, the inital containment cleanup and decontamina-tion has minimized the need for extensive use of temporary contain-ments such as tents and glove boxes to control the spread of conta-mination.
In areas where significant cutting and grinding work must be performed on highly contaminated piping and components, however, temporary containments have been constructed and are being effectively utilized.
The most significant application of this technique has been made in the lower steam generator cubicles, where the removal of reactor coolant and miscellaneous piping is performed.. In Unit No. 1, the lower cubicle for each steam generator has been totally enclosed to transform the entire room into a sing~e containment.
Portable ventilation units continuously draw air from these enclosures through appropriate filters whenever cutting or grinding operations are in progress.
Personnel working inside the cubicles are requir-ed to wear respiratory protection equipment during these opera-tions, and until the ventilation flow has effectively reduced the airborne radioactivity to acceptable levels.
Additional tent enclosures have been constructed in various loca-tions to provide controlled work areas for pipe cutting, component refurbishment and equipment decontamination.
Portable, filtered ventilation is provided to these enclosures as appropriate.
The benefits observed to-date for these ALARA techniques are three-fold.
(a)
The use of small glove boxes for individual pip~ cuts has been eliminated.
These devices require considerable time and exposure to install and remove, and during the Unit 2 SGRP were found in many cases to be counter-productive to ALARA due to this fact.
1, 3.7 e
. -**---.~--
PRl-10 SSGP (b)
The use of temporary containments, especially as applied to the lower steam generator cubicles, has largely eliminated delays and interference with work being performed in adjacent areas while cutting and grinding of contaminated piping is in progress.
(c)
The overall potential for airborne contamination and problems associated with contamination control have been minimized by effective use of temporary containments and portable ventila-tion.
General Techniques and Practices In addition to the specific dose reduction techniques described thus far, it is important to note the more general procedures and practices which have been implemented to assure adequate control of occupational radiation exposure and to maintain this exposure ALARA.
These include:
(a)
A comprehensive health physics program to provide adequate control and surveillance of the radiation hazards associated with each task.
This program includes the use of Radiation Work Permits (RWP' s) with an individual "sign-in" system to ensure worker familiarization with the specific radiological hazards involved and proper protective measures to be taken in the performance of their work.
(b)
A training program to provide adequate instruction in the biological effects of radiation exposure, radiation protection practices and applicable federal regulations, to all personnel involved in steam generator replacement activities.
Training for specific tasks, using mock-ups, photographs, or "dry runs" is conducteq where appropriate.
Additionally, the video-tape documentation compiled during the Unit No. 2 SGRP is being utilized to provide all personnel with a general understanding of the repair program.
In this way, each worker is more fami-liar with the sequence of events to take place ~nd the manner in which individual tasks relate to the overall repair effort.
i PRl-11 SSGP (c)
The use of discrete "Work Packages" to assure adequate pre-planning and review of specific tasks, with special emphasis placed on minimizing the radiation exposure to personnel involved.
(d)
The establishment of rest areas" to accommodate workers during idle periods.
Rest areas within the containment are located where exposure rates are low (2-3 mR/hour on the average).
Additionally, for the Unit 1 replacement a "rest trailer" has been located outside the containment equipment hatch on the operating deck level where radiation levels are typically 0.1 mR/hour.
These rest areas are well posted for identification and workers are encouraged to utilize these areas whenever possible to avoid unnecessary exposure.
Although quantitative assessments are not possible for these "general" techniques, all have obvious value in contributing to the overall ALARA program for the steam generator replacement project.
~- --
PRl-12 SSGP 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General Radioactive liquid and gaseous effluents, and radioactively conta-minated solid wastes generated during the SGRP for Unit No. 1 are attributable to several sources.
In general, these sources can be distinguished with reasonably accuracy from those associated with concurrent operation of Unit No. 2, even though shared processing systems are utilized in some cases.
4.2 Airborne Releases 4.3 Airborne releases during the reporting period originated primarily from the initial purging of containment following shutdown, coolant de-gassing operations during defueling, and, to a smaller degree, the continuous ventilation of the containment during the repair effort, to maintain a negative pressure while the equipment hatch is open.
This continuous ventilation is processed through appro-priate filter banks to minimize the concentration of airborne particulates which may result from activities inside the contain-ment.
Liquid Releases Small amounts of liquid wastes were generated during the initial shutdown and defueling phase from draining and sampling operations.
- However, the major contributor to liquid releases during this reporting period is disposal of laundry waste water.
Laundry wastes are* expected to comprise the predominant source of liquid releases during the remainder of the repair effort, as was observed during the SGRP for Unit No. 2.
4.4 Solid Radioactive Waste The disposal of contaminated insulation, structural material, and piping and components not intended for reuse has been the major source of solid radioactive waste for the reporting period.
Conta-minated paper waste, disposable protective clothing and contamina-tion control materials also contributed to the total waste volume for this period.
The total volume of solid radioactive waste
PRl-13 SSGP requiring disposal as a result of the Unit 1 SGRP is expected to be somewhat lower than that observed for Unit 2.
Additional waste compaction equipment (a box compactor) is being used which allows more efficient*packaging of solid waste materials.
Waste materials such as insulation which previously were packaged loosely in large boxes, can now be compacted in the shipping container.
Wasted space is thus minimized and packaged volumes reduced.
The quantities of radioactive materials released in liquid and gaseous effluents, and the amounts of solid radioactive waste shipped offsite for disposal during this reporting period are summarized in Table 2.
PHASE DESCRIPTION I
Shutdown and Preparatory Activities II Removal Activities III Installation Activities IV Poet Installation and Startup Activities V Steam Generator Storage Activities PROJECT TOTALS (Completed Tasks Oniy)
TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES -
REPORT PERIOD 9/14/80 - 10/31/80 SURRY POWER STATION - UNIT NO. l
- ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED LABOR TO-DATE
. EXPOSURE PERIOD TO-DATE
{MANHOURS)
{MANHOURS~
~MAN-REM~
~MAN-REM)
{MAN-REM~
- COMPLETED TASKS ONLY***
18,717 25,880 206.37 103.365 103.365 3,084 4,564 50.70 30.907 30.907 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
21,801 30,444 257.07 134.272 134.272 PAGE 1 of 14 PHASE STATUS (C*COMPLETE)
{I*IN PROGRESS~
I I
I I
I
PAGE 2 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES -
REPORT PERIOD 9/14/80 - 10/31/80 SURRY POWER STATION -
UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE e
ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS PHASE LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION
~MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM~
(I"'IN PROGRESS)
- ALL TASKS COMMENCED AS OF 10-31-80***
I Shutdown and Preparatory 39,021 41,386 596.27 175.903 175.903 I
Activities II Removal Activities 57,422 35,487 559.6 144.046 144.046 I
III Installation Activities 74,195 2,703 448.23 5.566 5.566 I
IV Post Installation and 62,650 1,504 427.54 3.141 3.141 I
Startup Activities V Steam Generator Storage 300 0
35.0 0
0 I
Activities e
PROJECT TOTALS 233,588 81,080 2,066.64 328.656 328.656-(All Tasks)
l PAGE 3 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I -
SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK e
ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C.,COMPLETE)
. DESCRIPTION (MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
~I"'IN PROGRESS)
Erect Equipment Hatch 264 0
0.4 0
0 I
Temporary Enclosure Prepare and Load Test 210 462 1.05 1.277 1.277 C
Polar Crane Open Equipment Hatch 156 0.23 C
(See Note 1)
Defueling and Fuel Storage 585 2,863
- 11. 7 23.503 23.503 C
Install Reactor Vessel 130 695 1.3 1.813 1.813 C
Cavity* Cover Cutting of Pressurizer (See Note 2)
Cubicle Wall e
Installation of Jib Cranes 1,838 2,426 9.19 3.767 3.767 I
Disassemble Manipulator Crane 58 613
- 1. 74 1.533 1.533 C
Install Ste'am Generator 572 1,295 2.86 1.636 1.636 I
Transport System Removal of Biological 1,296 892 19.44 2.249 2.249 C
Shield Wall
I PAGE 4 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I -
SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (CmCOMPLETE)
DESCRIPTION (MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
~I=IN PROGRESS)
Disassemble Shroud Cooling 150 525 3.0 1.138 1.138 C
System Cutting of Crane Wall at 432 496 2.16 0.823 0.823 C
Hatch Opening Installation of Temporary 50 53 0.05 0.047 0.047 I
Ventilation System Temporary Scaffolding 7,500 3,071 75 9.506 9.506 I
Temporary Lighting 5,200 1,533 26.25 1.701
- l. 701 C
and Power Cleanup and Decon 9,000 14,920 135 57.975 57.975 C
Polar Crane Operator 1,500 198 4.5 0.137 0.137 C
Shielding 3,600 1,150 270 45.428 45.428 I
H.P., Q.A.
I 6,480 6,884 32.4 9.956 9.956 I
ADDITIONAL TASKS Installation of Service 627 2.198 2.198 I
Air System
PAGE 5 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I -
SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION -
UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION (MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
{IaIN PROGRESS)
Work Platform Modification 1,802 0.741 0.741 C
Protection of Containment 881 4.211 4.211 N/A Components UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 6.264 6.264 N/A and Administration Visitors and Inspectors 0
0 N/A Subtotal Phase I 18,717 25,880 206.37 103.365 103.365 (Completed Tasks Only)
PAGE 6 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II -
REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION (MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
(!=IN PROGRESS)
Removal of Insulation 720 1,647 28.8 14.000 14.000 C
(lower shell, RC Piping)
Removal of Insulation (upper shell, 864 870 12.96 4.843 4.843 C
mainsteam and feedwater piping)
Removal of Miscellaneous 72 1,116
- 1. 8 10.181 10.181 C
Piping Set Up Steam Generator 1,152 35 28.8 0.195 0.195 I
Girth Cut Equipment Cut and Remove Steam 330 323 8.25 0.930 0.930 I
Genera~or Upper Shell Cutting of Reactor 2,982 4,551 149.1 45.881 45.881 I
Coolant Piping Cutting of Mainsteam and 1,428 931 7.14 1.883 1.883.
C e
Feedwater Piping Disassembly of Steam 792 2,598 15.84 19.884 19.884 I
Generator Supports Removal of Moisture 396 541 Separation' Equipment 1.98
- l. 782 1.782 I
Refurbish Steam Generator 9,246 485 46.23 0.703 0.703 I
Upper Shell
PAGE 7 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II -
REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO, 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK e
ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION
~MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
(I*IN PROGRESS)
Removal of Steam Generator Level 135 287 4.05 1.028 1.028 I
Instruments and Blowdown Piping Removal of Steam Generator 1,575 0
31.5 0
0 I
Lower Shell Temporary Scaffolding 7,500 3,070 75.0 9.506 9.506 I
Temporary Lighting and Power 5,250 1,532 26.25 1.701 1.701 I
Cleanup and Decon 17,000 5,156 85.0 8.589 8.589 I
Polar Crane Operator 1,500 0
4.5 0
0 I
H.P., Q,A, 6,480 6,884 32.4 9.955 9,955 I
e ADDITIONAL TASKS Material Handling, Equipment Maintenance, and Miscellaneous Construction Activities 5,,461
- 6. 722
- 6. 722 N/A
TASK DESCRIPTION UNASSIGNED PERSONNEL CATEGORIES Project Supervision and Administration Visitors and Inspectors Subtotal Phase II (Completed Tasks Only)
ESTIMATED LABOR (MANHOURS) 3,084 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II -
REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR EXPENDED TO-DATE (MANHOURS)
Not Reported II 4,564 ESTIMATED EXPOSURE (MAN-REM) 50.70 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM) 6.263 0
30.907 ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM) 6.263 0
30.907 PAGE 8 of 14 TASK STATUS (C 3 COMPLETE)
(I*IN PROGRESS)
N/A N/A
PAGE 9 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III -
INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION
~MANHOURS)
(MANHOURS)
(MAN-REM)
~MAN-REM)
(MAN-REM~
~I*IN PROGRESS)
Steam Generator Lower 1,926 163 9.63 0.361 0.361 I
Shell Installation Installation of Reactor 6,768 1,027 67.68 2.078 2.078 I
Coolant Piping Steam Generator 5,400 1,513 27.0 3.127 3.127 I
Girth Weld Installation of 3,735 0
18.68 0
0 I
Main Steam Piping Installation of 2,700 0
13.5 0
0 I
Feedwater Piping Installation of Blowdown and 1,782 0
17.82 0
0 I
Miscellaneous Piping Install Steam Generator 2,592 0
12.96 0
0 I
Level Instruments Installation of 11,562 0
- 57. 81 0
0 I
Insulation Temporary Sc,affolding 7,500 0
75.0 0
0 I
Temporary Lighting 5,250 0
26.25 0
0 I
& Power
TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III -
INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ESTIMATED EXPENDED ESTIMATED FOR REPORTING TASK LABOR TO-DATE EXPOSURE PERIOD DESCRIPTION (MANHOURS)
~MANHOURS)
(MAN-REM)
(MAN-REM)
Cleanup and Decon 17,000 0
85.0 0
Polar Crane Operator 1,500 0
4.5 0
H.P., Q.A.
6,480 0
32.4 0
ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 0
0 UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 0
and Administration Visitors and II 0
Inspectors I
Subtotal Phase III 0
0 0
0 (Completed Tasks Only)
ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM~
0 0
0 0
0 0
0 PAGE 10 of 14 TASK STATUS (C*COMPLETE)
~I*IN PROGRESS)
I I
I N/A N/A N/A
'*' ~-
e e
-1
I
, I PAGE 11 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV -
POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)
DESCRIPTION
~MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM~
{ImIN PROGRESS)
Install Biological 3,240 20 16.2 0.034 0.034 I
Shield Wall Repair Crane Wall 473 57 2.37 0.063 0.063 I
Opening Repair Pressurizer Cubicle (See Note 2)
Wall Install Steam Generator 9,000 1,315 90.0 2.705 2.705 I
Recirculation and Transfer System Remove Reactor Cavity 130 0
0.65 0
0 I
Cover Install Reactor Cavity 240 0
1.2 0
0 I
Coaming Reassemble Manipulator 1,176 112 23.25 0.339 0.339 I
Crane Remove Steam Generator 425 0
2.12 0
0 I
Transport System Reassemble Shroud 576 0
- 11. 52 0
0 I
Cooling System Hydrostatic Tests 75 0
0.38 0
0 I
PAGE 12 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV -
POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK e
ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (CmCOMPLETE)
DESCRIPTION
~MANHOURS)
(MANHOURS)
(MAN-REM)
(MAN-REM)
(MAN-REM)
~I*IN PROGRESS)
Refueling 585 0
- 11. 7 0
0 I
Temporary Scaffolding 7,500 0
75.0 0
0 I
Temporary Lighting 5,250 0
26.25 0
0 I
and Power Cleanup and Decon 17,000 0
85.0 0
0 I
Polar Crane Operator 1,500 0
4.5 0
0 I
Painting 9,000 0
45.0 0
0 I
H.P., Q.A.
6,480 0
32.4 0
0 I
ADDITIONAL TASKS Material Handling, Equipment Maintenance1 and Miscellaneous Construction Activities 0
0 0
N/A
TASK DESCRIPTION UNASSIGNED PERSONNEL CATEGORIES Project Supervision and Administration Visitors and Inspectors Subtotal Phase IV (Completed Tasks Only)
ESTIMATED LABOR (MANHOURS) 0 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION -
UNIT NO. 1 ACTUAL LABOR EXPENDED TO-DATE (MANHOURS)
Not Reported II 0
ESTIMATED EXPOSURE (MAN-REM) 0 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM) 0 0
0 ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM) 0 0
0 PAGE 13 of 14 TASK STATUS (C*COMPLETE)
(IzIN PROGRESS)
N/A N/A
TASK DESCRIPTION Steam Generator Storage Activities ESTIMATED LABOR (MANHOURS) 300 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE V -
STEAM GENERATOR STORAGE ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE EXPENDED ESTIMATED FOR REPORTING TO-DATE EXPOSURE PERIOD (MANHOURS)
(MAN-REM)
(MAN-REM) 0 35.0 0
TABLE NOTATION ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM) 0 PAGE 14 of 14 TASK STATUS (C*COMPLETE)
(I*IN PROGRESS)
I
- 1.
Labor and Exposure expend! tu res for this task were included in other task totals.
(Primarily "Defueling and Fuel Storage").
Labor and Exposure estimates are included in the Subtotal Values.
- 2.
This task was cancelled due to equipment changes.
Labor and Exposure Estimates are not included in the Subtotal Values.
N/A - Not Applicable, Labor and Exposure Expenditures are included in the Subtotal Values for Phase I.
They are not included in the Subtotal Values for Phases II, III and IV (See Report Section 2.3.c).
I.
JABLI 2 SURRY POWER STATION STEAM GENF.RA'(OR REl'LACEMl~f PRO.JFf!.
REPORT OF RADIOACTIVE lffFLUF.NTS September UN1:TS LIQUID UL!AS!S Curies I11otooe Released MPC uci/ml T-131 3 -x 10-'
5 96E-5 T-132 8 X 10-6 1-133 1 X 10-6 I-134 2 X 10-~
1-135 4 X l.V-"
Cll-134 9 X 10_.,.
3.0lE-4 C11-137 2 X 10-*
l.Ol1E-3 Co-57 4 X lO-*
Co.-5H fJ X 10-~
S,73E-4 Co-liO 3 X 10-5 1.lOE-3 Hn-54 1 X lO-*
3.36E-S Na-24 3 X 10-*
Cr-51 2 X lO-*
l.99E-4 Fe-59 5 X ]Q-"
Nb-95 l
Y 10- 4 l.llE-5 Sb-124
... 1 "-"
Sb-125, 1 v,n_"
Zn-o::,
l.,. in-"
Zr-'!I::,
6,r 10-~
Ho-99 4,r 10-5 Ru-103 8 X 10-5 Xe-133 3 X 10-11 8,66E-'i Xe-135 3 X 10-"
Xe-13311 3 X 10-6 Ar-41 3 X 10-6 A2-11om 3 X 10-~
Ni-o.J 3 X 10-5 Fe-55 8 X 10-"
Ce-144 l X lU-"
Tc-99m J X lU-*
Ce-141
'!IX 10-*
Volume of Liauid to Di1charge Canal IT_t.. a--
6.70E+4
- Hot Detected
- Sample analy1ia reault* not yet received from service vendor.
Upon receipt, analyaia data will be submitted ae a supplement to thia report
- October
/,. Q1F-'i 1 71F-6 8.32E-4 2.3BE-3 3.0lF-'l 5 72E-3 l llE-6 l.17E-3 4.B7E-/,.
S.68E-5 3.86E-5 1.89E-6 4, 74E-4 7.48E-S l.lSE-5 B.3BE-7 1r 9.0BE-7 S.89E+S PACI-'- or 2
YEAR:
1980 t
tit:
II.
ArRIORHI ULIASIS i-1sotones le!easei!:
......,........,~
(a)
Particulates Cs-134 Cs-lj/
Cr-51 Co-58 Co-60 Mn-54 Fe-59 Cs-138 Rb-88
~bJ Halogens I-l,31 I-132 I-111 T-1"11.
T-1'\\"i
(,.\\ l'.!aaan Ye-131 Xe-133m Xe-135 Kr-8Sm Kr-85 Kr-87 Kr-88 Ar-41 Xe-l31m H-3 III.
SOLID RADIOACTIVE WASTE DISPOSAL (a) Total Amount of Solid Waste Packaged (bJ -Estimated Total Activity (CJ Date of Shipment and Diapollition
.TABLE 2
~URRY POWER STATTON STF.AH GENEIU\\'fOR REPJ,ACEMENT PROJECT REPORT 01' RADIOAC'rrVE l~fo'FUmNTS
-.-.-~-............ ~
... :9---.-.
I UNITS
__......_.. **~......
September October eur1.;;~
2 ~
.. -_.......,.... -,..-~- -..... -~
~
J.l2E-6 1.22E-6 9.07E-6
- 1. 76E-5 4.42E-5 l.65E-5 2.63E-5 5,02E-5 J,49E-.5 6,95E-5 lllr lllr lllr lllr lllr i.76E-5 lllr "i ?/,1>-"i 1.78E-3
" liE::._4._
4,73E-~
lllr 2.12E-6 2 31E-5 lllr lllr lllr lllr 4.44E+2 lllr 5.22EO lllr 7,89EO lllr 3.21E-1 lllr lllr lllr lllr lllr lllr lllr lllr S,45E+2 lllr 7.0BE-1 2,l5E-1 FT' 0
3,94E+3 curies 0
l,448E+o 10-15-~
0 10-21-80 l-
- -~--*.. ~-...... - --......--r-....,_..._
10-23-80 I
W,::~8-:80~, *. ----------
- Not Datacted Barnwell I S, C, 10-30-80 PACI 2
OF 2
YFA!l* r 1980
?
I I
- 1.
I f
L I
. ~
I I
-