ML18139B032
| ML18139B032 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/30/1981 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139B031 | List: |
| References | |
| NUDOCS 8102020376 | |
| Download: ML18139B032 (31) | |
Text
' e STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 1 RADIOLOGICAL PROGRESS REPORT - NO. 2 FOR THE PERIOD NOVEMBER 1, 1980 THROUGH DECEMBER 31, 1980 DOCKET NO. 50-280 LICENSE NO. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY
e TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
PR2-1 2.0 OCCUPATIONAL RADIATION EXPOSURES PR2-2 2.1 General PR2-2 2.2 Evaluation of Exposure Data PR2-2 2.3 Description and Format of Exposure Data PR2-3 2.4 Conclusions and Observations PR2-4 3.0 APPLICATION OF ALARA PRINCIPLES PR2-5 3.1 General PR2-5 3.2 Containment Cleanup and Decontamination PR2-5 3.3 Temporary Shielding PR2-5 3.4 Steam Generator Water Level PR2-7 I
3.5 Plasma-Arc Cutting Equipment PR2-7 3.6 Temporary Containments and Ventilation PR2-8 3.7 Machining of Reactor Coolant Pipe Stub Ends PR2-9 3.8 Painting of Old Steam Generators PR2-9 3.9 General Techniques and Practices PR2-9 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR2-11 4.1 General PR2-11 4.2 Airborne Releases PR2-11 4.3 Liquid Releases PR2-ll 4.4 Solid Radioactive Waste PR2-11 TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents
PR2-l SSGP
1.0 INTRODUCTION
The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 1 commenced on September 14, 1980. This second 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 November 1 through December 31, 1980.
With regards to radiological effects, the major tasks completed during the reporting period involved the removal activities and some of the installation activities. These included the removal of reactor coolant piping, main steam and feed water piping and miscellaneous piping and disassembly of the steam generator supports; the cutting and removal of the upper shells and removal of the lower shells from the containment; the three new lower shells were installed in the containment and refurbishment of the old upper shells was started.
The report sections which follow provide an assessment of the occupational exposure expended, the dose reduction techniques employed and their effectiveness, a'nd 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.
.. e PR2-2 SSGP 2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General 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 upon 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 Generator 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 phase. 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.
i e PR2-3 SSGP 2.3 Description and Format of Exposure Data 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 December 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 attributable 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 Phases I and II (Shutdown and Preparatory Activities and Removal Activities). For Phases III and IV, The Phase Subtotals do not yet include the expen-ditures mentioned above since a majority of the tasks have yet to be commenced and/or completed.
e PR2-4 SSGP 2.4 Conclusions and Observations As of the end of the reporting period, the SGRP for Unit No. 1 has been in progress for approximately sixteen weeks. It is becoming apparent at this point in the outage that less exposure is being accumulated in comparison to the Unit 2 outage. This is attribu-table to a number of factors. Many of the workers and supervisors are the same ones that performed the work on Unit 2 so they are familiar with the work. In addition steps were taken in the preparation for the Unit 1 outage to eliminate problems encountered in Unit 2 and to stream line the procedures. A comparison of the exposure attributable to reaching the same milestone events in Unit 2 that have now been reached in Unit 1 shows that Unit 2 took about 1050 man-rem to reach the same point that Unit 1 took 792 to reach or a savings of about 238 man-rem. It also should be noted that these milestones were reached in Unit 1 about 45 days earlier than in Unit 2.
PR2-S SSGP 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General This section summarizes the specific techniques and practices which were employed during this reporting period in order to maintain occupational exposures to radiation "as low as reasonably achiev-able" (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 Containment 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 sue-
e e PR2-6 SSGP cessful in minimizing exposure rates for subsequent activities, the task of installing the shieldint 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 thus far during the SGRP has totaled 57 man-rem. 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 radiation 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 remova'l of miscellaneous piping located in the steam generator cubicles, has continued during this reporting period and has now totaled approximately 14 man-rem. Lead shielding resulted in dose reduction factors of about 5 as described in PRl which results in a total calculated exposure savings of 56 man-rem.
(b) The cutting and removal of reactor coolant piping has resulted in the expenditure of about 77 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 385 manrem to-date.
The assessments described above represent a major portion of the overall benefits expected to result from the application of temporary shielding techniques during the SGRP. All of the removal
~ PR2-7 SSGP activities have been completed at this time. There are however, installation activities still to be performed which will benefit from the shielding already in place. 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 Generator Level Instrumentation and Blowdown Piping.
All of these tasks were completed during this reporting period with a total expenditure of about 23 man-rem. This results in a calcu-lated savings of about 207 man-rem.
3.5 Plasma-Arc Cutting Equipment The plasma-arc cutting of the reactor coolant piping was completed during this reporting period with a total expenditure of about 77 man-rem. This compares to the Unit 2 outage in which 214 man-rem was expended for this operation.
e PR2-8 SSGP 3.6 Temporary Containments and Ventilation 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 single 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 pipe 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.
e PR2-9 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.
3.7 Machining of Reactor Coolant Pipe Stub Ends A different type of machining equipment has been utilized on Unit No. 1 to weld prep the reactor coolant pipe stub ends in the steam generator cubicle. The machine utilizes micro-processor control of the machining operations with the operators console on the end of a pendant so that. most of the machining operation can be controlled from a distance.
3.8 Painting of Old Steam Generators During the Unit 2 steam generator replacement the old lower assemblies were decontaminated by wiping them down with alcohol to remove loose surface contamination. During the Unit 1 outage paint was used to fix this loose surface contamination which could be done much more rapidly than the cleaning done during Unit 2 thereby resulting in a reduction in exposure.
3.9 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 s~rveillance of the radiation hazards associated with each task. This program includes the use of Radiation
PR2-10 SSGP 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 conducted 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 and the manner in which individual tasks relate to the overall repair effort.
(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.
PR2-11 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 Airb_orne releases during the reporting period originated primarily from 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 appropriate filter banks to minimize the concentration of airborne particulates which may result from activities inside the contain-ment. The presence of radioactive halogens (I-131 and I-133) and noble gases (Xe-133) has been noted in the ventilation exhaust during the reporting period. These radionuclides, however, are attributed to the operation of Unit No. 2 and originated from sources within the Auxiliary Building.
4.3 Liquid Releases The major contributor to liquid releases during this reporting period continues to be 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.
PR2-12 SSGP 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.
PAGE l of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 11/1/80 - 12/31/80 SURRY POWER STATION - UNIT NO. l ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE 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)
- COMPLETED TASKS ONLY***
I Shutdown and Preparatory 35,107 45,825 325.82 15.460 145.888 C Activities II Removal Activities 48,176 144,325 513.37 283.029 426.372 C III Installation Activities 0 0 0 0 0 I IV Post Installation and 0 0 0 0 0 I Startup Activities V Steam Generator Storage 300 937 35 8.079 8.079 C Activities PROJECT TOTALS 83,583 191,087 874.19 306.56"8 580.339 (Completed Tasks Only)
PAGE 2 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 11/1/80 - 12/31/80 SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE 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 12-31-80***
I Shutdown and Preparatory 39,021 47,774 596.27 27.494 203.397 C Activities II Removal Activities 57,422 150,343 559.6 288.416 432.462 C III Installation Activities 74,195 56,447 448.23 123.650 129.216 I IV Post Installation and 62,650 5,919 427.54 15.924 19.065 I Startup Activities V Steam Generator Storage 300 937 35 8.079 8.079 C Activities PROJECT TOTALS 233,588 261,420 2,066.64 463.563 792.219 (All Tasks)
PAGE 3 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) (I=IN PROGRESS)
Erect Equipment Hatch 264 0 0.4 0 0 I Temporary Enclosure Prepare and Load Test 210 463 1.05 0.008 1.285 C Polar Crane Open Equipment Hatch 156 0.23 C (See Note 1)
Defueling and Fuel Storage 585 2,863 11. 7 0 23.503 C Install Reactor Vessel 130 695 1.3 0 l. 813 C Cavity Cover Cutting of Pressurizer (See Note 2)
Cubicle Wall Installation of Jib Cranes 1,838 3,307 9 .19 1.479 5.246 C Disassemble Manipulator Crane 58 629 l. 74 0 1.533 C Install Steam Generator 572 3,360 2.86 4.806 6.442 C Transport System Removal of Biological 1,296 916 19.44 0.049 2.298 C Shield Wall
PAGE 4 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I - SHUTDOWN ANO 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) (I=IN PROGRESS)
Disassemble Shroud Cooling 15D 601 3 0.090 1. 228 C System Cutting of Crane Wall at 432 496 2 .16 0 0.823 C Hatch Opening Installation of Temporary 50 103 0.05 0.006 0.053 I Ventilation System Temporary Scaffolding 7,500 4,632 75 4.745 14.251 C Temporary Lighting 5,200 2,133 26.25 0.433 2.134 C and Power Cleanup and necon 9,000 14,920 135 0 57.975 C Polar Crane Operator 1,500 198 4.5 0 0.137 C Shielding 3,600 1,846 270 12.028 57 .456 I H.P., Q.A. 6,480 6,884 32.4 0 9.956 C ADDITIONAL TASKS Ins tal la tion of Service 627 0 2 .198 C Air System
PAGE 5 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 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)
Work Platform Modification 1,816 0 0.741 C Protection of Containment 1,285 1.895 6.106 N/A Components UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 1.955 8.219 N/A and Administration Subtotal Phase I 35,107 45,825 325.82 15.460 145.888 (Completed Tasks Only)
PAGE 6 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 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 Insulation 720 1,647 28.8 0 14.000 C (lower shell, RC piping)
Removal of Insulation (upper shell, 864 959 12.96 0.511 5.354 C mainsteam and feedwater piping)
Removal of Miscellaneous 72 1,288 1.8 3. 715 13.896 C Piping Set Up Steam Generator 1,152 90 28.8 0.013 0.208 C Girth Cut Equipment Cut and Remove Steam 330 4,595 8.25 7.210 8.140 C Generator Upper Shell Cutting of Reactor 2,982 7,181 149.l 30.801 76. 682 C Coolant Piping Cutting of Mainsteam and 1,428 1,399 7.14 0.508 2.391 C Feedwater Piping Disassembly of Steam 792 6,830 15.84 34.183 54.067 C Generator Supports Removal of Moisture 396 3,675 1.98 6.133 7.915 C Separation Equipment Refurbish Steam Generator 9,246 6,018 46.23 5.387 6.090 I Upper Shell
PAGE 7 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 PF,RIOD TO-DATF, (C=COMPLETE)
DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I=IN PROGRESS)
Removal of Steam Generator Level 135 1,472 4.05 5.361 6.389 C Instruments and Blowdown Piping Removal of Steam Generator 1,575 4,319 31. 5 22.737 22.737 C Lower Shell Temporary Scaffolding 7,500 12,436 75 28.471 37.977 C Temporary Lighting 5,250 5,133 26.25 2.598 4.299 C and Power Cleanup and Decon 17,000 42,217 85 76.700 85.289 C Polar Crane Operator 1,500 2,175 4.5 2.367 2.367 C H.P., Q.A. 6,480 25,860 32.4 22.187 32.142 C ADDITIONAL TASKS Material Handling, Equipment 23,049 27.804 34.526 N/A Maintenance, and Miscellaneous Construction Activities
PAGE 8 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) (I=IN PROGRESS)
UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 11. 730 17.993 N/A and Administration Subtotal Phase II 48,176 144,325 513.37 283.029 426.372 (Completed Tasks Only) e
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 EXPENDED ESTIMATED FOR REPORTING EXPENDED e
ESTIMATED 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 6,263 9.63 14.293 14.654 I Shell Installation Installation of Reactor 6,768 4,257 67.68 32.188 34.266 I Coolant Piping Steam Generator 5,400 4,579 27 2.577 5.704 I Girth Weld Installation of 3,735 2,800 18.68 1.263 1.263 I Main Steam Piping Installation of 2,700 661 13.5 0.184 0.184 I Feedwater Piping Installation of Blowdown and 1,782 0 17.82 0 0 I Misc;ellaneous 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 Scaffolding 7,500 3,903 75 11. 863 11. 863 I Temporary Lighting 5,250 1,500 26.25 1.083 1.083 I
& Power
PAGE 10 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION 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) (I=IN PROGRESS)
Cleanup and Decon 17,000 15,883 85 32.872 32.872 I Polar Crane Operator 1,500 932 4.5 1.014 l.014 I H.P., Q.A. 6,480 8,132 32.4 9.509 9.509 I ADDITIONAL TASKS Material Handling, Equip- 7,537 11. 916 11. 916 N/A ment Maintenance, and Miscellaneous Construction Activities UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 4.888 4.888 N/A and Administration Subtotal Phase III 0 0 0 0 0 (Completed Tasks Only)
PAGE 11 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP 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 DESCRIPTION (C=COMPLETE)
(MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I=IN PROGRESS)
Install Biological 3,240 30 16.2 0.037 0.071 Shield Wall I Repair Crane Wall 473 81 2.37 0.007 0.070 Opening I Repair Pressurizer Cubicle Wall (See Note 2)
Install Steam Generator 9,000 4,427 90 11. 378 14.083 Recirculation and Transfer System I Remove Reactor Cavity 130 0 0.65 0 0 Cover I Install Reactor Cavity 240 0 1.2 0 0 Coaming I Reassemble Manipulator 1,176 127 23.25 0.007 0.346 Crane I Remove Steam Generator 425 3 2.12 0 0 Transport System I Reassemble Shroud 576 170 11. 52 0.930 0.930 Cooling System I Hydrostatic Tests 75 0 0.38 0 0 I
PAGE 12 of 14 TABLE l 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) (I=IN PROGRESS)
Refueling 585 0 11. 7 0 0 I Temporary Scaffolding 7,500 780 75 2.372 2.372 I Temporary Lighting 5,250 301 26.25 0.216 0.216 I and Power Cleanup and Decon 17,000 0 85 0 0 I Polar Crane Operator 1,500 0 4.5 0 0 I Painting 9,000 0 45 0 0 I H.P., Q.A. 6,480 0 32.4 0 0 I ADDITIONAL TASKS Material Handling, Equipment Maintenance, and Miscellaneous Construction Activities 0 0 0 N/A
PAGE 13 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 DESCRIPTION LABOR (MANHOURS)
TO-DATE (MANHOURS)
EXPOSURE (MAN-REM)
PERIOD (MAN-REM)
TO-DATE (MAN-REM)
(C=COMPLETE)
(I=IN PROGRESS) e UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 0.977 0.977 N/A and Administration Subtotal Phase IV 0 0 0 0 0 (Completed Tasks Only)
PAGE 14 of 14 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE V - STEAM GENERATOR STORAGE 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) (!=IN PROGRESS)
Steam Generator Storage 300 937 35 8.079 8.079 C Activities
===================================================================================================================================
TABLE NOTATION
- 1. Labor and Exposure expenditures 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 Phases I and II. They are not included in the Subtotal Values for Phases III and IV (See Report Section 2.3.c).
PAGE 1 of 3
- . TABLE 2 SURRY POWER STATION STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1980 I
September October Novemh.,.,. -
- - - ~ r - ..
UNlTS I. LIQUID RELEASES Curies Isotooe: Released HPC uCi/ml
- I-131 3 X 10- 1 5.96E-5 4 Q1F.-'i ? ?'iF.. .3
- 1-132 8 X 10-6 * * *
- I-133 1 X 10-6
- 1. 73E-6 l.32E-5 3.47E-7 -
I-134 2 X 10-* * * * * -
I-135 4 X 10-6 * * *
- Cs-134 9 X 10
- 1.89E-6 3.57E-7 Co.-5H g X 10-> 5.73E-4 3.011'-1 l.36E-2 !l.bOE-4 Co-ou 3 X 10-> l.lOE-3 r; 72E-3 l.BlE-2 3.48E-3 Mn-54 1 X 10-* 3.36E-5 l.llE 4 2.78E-3 4.45E-5 Na-24 3 X 10-a
- l.17E-3 6.29E-3
- fc Cr-51 2 X 10-, l.99E-4 4.87E-4 l.14E-4
- Fe-59 5
!i X 10- _ * * **
- Nb-95 1 Y 10-* l.llE-5 S.68E-5 3.66E-5 1 21F.-'i Sb-124 2 V 10 > *
- l.ZOE-6 -*
Sb-125 1 v 10-~
- 3.86E-5 7.SOE-7 1.44E-6 Zn-b5 1 X 1n_ ~ *
- 2.60E-6
- Zr-95 6 X 10- * * * *
- Mo-99 4 X 10- 5 * * *
- Ru-103 8 X 10-*
- 1.89E'-6 *
- Xe-133 J X 10-* 8.66E-5 4.74E-4 l.BSE-2 3.68E-6 Xe-135 J X 10-*
- 7.48E-5 2.41E-3 * '-
Xe-133m 3 X 10- 6
- l.lSE-5 *
- Ar-41 J X 10- 6
- 8.38E-7 *
- Ag-IIOiii 3 X 10- 5 * * *
- Ni-bJ 3 X 10- 5 4.0lE-5 1 41E-3 ** **
Fe-55 8 X 10- 0 l.16E-4 1.12E-2 ** **
Ce-144 1 X 10-* * * *
- Tc-99m j X 10- 3
- I. 77E-7
- Ce-141 9 X 10->
- 9.0BE-7 "
Volume of Liquid to Discharge Canal 'T:f t-c.-a 6.70E+4 S.89E+5 I.16E+6 4.76E+S
- Not Detected
- Sample analysis results not yet received from service vendor.
Upon receipt, analysis data will ~e submitted as a supplement to this report.
/
TABLE 2 PAGE 2 of_3_
SURRY POWER STATTON STEAM r.ENft{i\7fOR REPJ.ACl:'.HifN'i' PROJECT YEAR: 1980 REPORT 01' RAIHOACT TVE El'FUIENTS
--=--~-~ .. - . - . - - ~ - . -*- ---- - . - -*-- .. .. ::r - .--- ---~.~~==~~~~~~=-~-~
II. AIRBORNE RELEASES , . ~ * - - -.,.-r-'"?""- - . ---~ """"S:'T- . . * -.--*--** -
'UNITS September October N~vemher 'December
,*,**1:r*s-0..t-o~pes-R!!"e'"<il"'e_a_s~e~d-:- ~ ~ ~ ~ ~ * - * * .*.. ' ~ CITT!e-;. ~--**-***-**** *~ ~. -****-***-
(a} Particulates *--- - * ---H------lr-::--*:::::=--7""--lt-------1t------*lt------t------l~
Ce-134 3.12E-6 1.22E-6 -
- 2.73E-6 -
Cs-137 9.07E-6 1. 76E-5__ [_Ll6E-5 2 .21E-5 Cr-51 4.42E-5 1. 65E - > - -*- - - - -
Co-58 2.63E-5 5.02E-5 1.65E-5 -*
- 1.94E-5 Co-60 3.49E-S ~~ S.97E-S 6.27E-5
"M-'-n_:-"-5-'-4-------------
Fe-59 Cs-138 1.0lE-4 *
- Rb-88 *
- 5 ?b.F 5 * *
(b) Halogens I-1)1 1. 78E-3 6 l,5E-4...__ 7.90E-4 l.74E-5 II I-132 4. 73E.=§_ * *
- l .31E-6 1
I-133 2.12E-6 2.31E-S 4.03E-5 I-134 * * *
- T-1 'l.~
(c) Gases Xe-133 4.44E+2
- S.26E+l
- Xe-133m 5.22EO * *
- 7 .89EO *
- Xe-135 *
- Kr-85m - - - ~ -3.- 21E-1 tt~-- * - l l - -*- , - - -*l ~ - - - - - - ! I - - - - '
o-----K~r~-~8~5__________________,..._ ___,,_ _*_ _ _ _,r-------tt-- *
- Kr-87 * *
- Kr-88 * * *
- Ar-41 * * " "
Xe-131m S.45E+2 H-3 7 .08E-l 2.lSE-1 6.97E-2 5.62E-2
l!--*- ------H*------11--------~-------11-----4------11------11-------H I - - - - - - - - - - - - - - - - - - - - - - -*- - - I*--****-- -------~---- ------11------4\-------ll------~------!f---------
**- -- -- -** - .... li- -- ***-* I - - -----** **-->------* *-*---- - - - - - - - - - - - - - - - 1 1 - - - - - - l l - - - - - - l f - - - - - - l l - - - - - - ~ - - -*
... ___ ,____ ..... -----*-*---*** ~~........,,~~~-......---.----*----~
- Nut Detected
TABLE 2 SURRY POWER STATION PAGE 3 of 3 STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENT~ YEAR: 1980 III. SOLID RADI0.11.ETIVE WASTE DISPOSAL ~- - -- - -- - -- ~ -- -- -w =~ *-
j Units C:o~t-.omh-~. ' !
Ort-~i,.,r De,..<>mhpr I, Isotopes Released: Curies - -* - - - ---- -- =-- - - - ,.r=
I *u (a) Total Amount of Solid Haste Packaged FT 3 0 3.94E+J 6.30E+3 l.64E+4 (b) Estimated Total Activity Curies 0 1 .45E+o l.82E+l 8,54E+o (c) Date of Shipment and A11 to
~:~well,
!11 to sa;::nwell,
~Hrnewell to Disoosition . _o .. s r.
10-15-80 11-J-Rn 12-1-80 2)
- .. 10-21-80 11-4-80 12-2-80 2) 10-23-80 11-6-80 12-3-80 2)
-- 10-28-80 11-7-80 (2) 12-4-80 2)
- 10-30-80 11-10-Rn 12-5-80 2) 11-12-80 12.-8-80
' 11-11-80 12-11-80(2) 1 11-14-80 12-I2-80
- - 11-18-80(2) 12-15-80
-- 11-19-80 12-16-80 12-17-80 12-18-80 12-19-80 12-22-80*
12-3_0-80(2)
II I -*
--- -- --* - ._ *- - *... - - - - - - - --- . - . . -- - - - - - - - - - - - - ~ = - : . - * . . . . * . . * . * ** - - - ~ - - - - - - * * * - - - - - - - - -- - - - - --- - - - - ~ ~ --- - - - . ~~ ~~----*-*- - - -- ~~~~~*--- --