ML18136A150
| ML18136A150 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/30/1979 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18136A149 | List: |
| References | |
| NUDOCS 7911060300 | |
| Download: ML18136A150 (31) | |
Text
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STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION
. UNIT NO. 2 PROGRESS REPORT - NO. 4 FOR THE PERIOD AUGUST 1, 1979 THROUGH SEPTEMBER 30, 1979 DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY
TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
PR4-l 2.0 OCCUPATIONAL RADIATION EXPOSURES PR4-2 2.1 General PR4-2 2.2 Evaluation of Exposure Data PR4-2 2.3 Description and Format.of Exposure Data PR4-3 2.4 Conclusions PR4-4 3.0 APPLICATION OF ALARA PRINCIPLES PR4-5 3.1 General PR4-5 3.2 Temporary Shielding PR4-5 3.3 Miscellaneous Valve Refurbishment PR4-6 3.4 Training PR4-7 3.5 General Techniques PR4-8 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR4-9 4.1 General PR4-9 4.2 Airborne Releases PR4-9 4.3 Liquid Releases PR4-9 4.4 Solid Radioactive Waste PR4-10
5.0 CONCLUSION
S PR4-ll TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents
PR4-l SSGP
1.0 INTRODUCTION
This Progress Report contains information on the radiological effects of the Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 2, and the measures taken to maintain these effects "as low as is reasonably achievable" (ALARA), during the period August 1 through September 30, 1979.
With regard to radiological effects, significant tasks performed during the reporting period involved installation activities and included: ins*tallation of removed reactor coolant pipe sections, installation of main steam piping, and installation of blowdown and miscellaneous piping. Installation of the steam generator recir-culation and transfer system, as well as ongoing peripheral and support activities (temporary scaffolding, cleanup and decontamina-tion, health physics support and project supervision) also contri-buted significantly to the total radiological effects assessed during this period.
The report sections which follow provide an assessment of the occu-pational radiation exposure expended, the dose reduction techniques employed and their effectiveness, and the radioactive effluents and solid waste generated during the reporting period.
PR4-2 SSGP 2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General Occupational exposure to radiation may be considered the major radiological effect of the SGRP. Thus, significant importance has been placed upon providing an accurate assessment of the collective radiation exposure which is expended in performing each of the tasks involved. Estimates of these exposures 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.
2.2 Evaluation of Exposure Data The program established to assess the actual exposures received during the repair effort has been designed to provide data which is compatible with the detail and format of the exposure summary pre-sented in Table 5.3-1 of the SGRP report. This design permits valid comparisons between the estimated and actual exposures for specific tasks. In general, the program utilizes daily worker exposure data, as recorded by self-reading pocket dosimeters, in conjunction with contractor supplied, worker task data to evaluate current manrem expenditures. The worker task data is standardized to a system of discrete work packages (called Engineering Task Ass'ignments) which was developed during the project planning phase.
The use of this system to categorize exposure related work for in-dividuals on a daily basis facilitates the process of compiling an accurate breakdown of the collective exposure expended on the many tasks involved. A more detailed description of this program, and
'l ! _ __
PR4-3 SSGP the basis for its design, was presented in Section 2.2 of Progress Report No. 2 for the SGRP.
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 February 3, 1979 to September 30, 1979), 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: included in Table 1. Similarily, exposures received by personnel per-forming 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.
PR4-4 SSGP (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 Categories" are allocated to a particular phase based upon the major acti-vities being performed at the time they are incurred. Thus the Phase Subtotals also include these values for phases which can be considered essentially complete. This is the case for Phase I (Shutdown and Preparatory Activities) and Phase II (Removal Activities). For Phase III (Installation Activities), and Phase IV (Post Installation and Startup Activities) the Phase Subtotals do not yet include the expendi-tures mentioned above since a majority of the tasks involved in these phases have yet to be completed.
2.4 Conclusions A review of the data presented in Table 1 of this report reveals that the total occupational radiation exposure received for tasks completed as of September 30, 1979 is approximately 9% below the original estimate. Furthermore, no worker assigned to the SGRP has to date received radiation exposure in excess of applicable federal standards. These facts, and the exposure reductions effected by the techniques described in Section 3 of this report, illustrate clearly that the committment to maintairi occupational exposures ALARA is being successfully applied to the repair effort.
PR4-5 SSGP 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General This section summarizes the specific dose reduction techniques employed during the reporting period. Some of the techniques described were implemented prior to this period; however, their continued application and effectiveness have provided significant benefits (exposure reductions) to a number of tasks performed dur-ing August and September. Where the available data permits, the following evaluations include a quantitative assessment of the man-rem savings which can be attributed to the technique used. Addi-tional information on the techniques discussed, and how they relate to the overall steam generator replacement activities can be found in the SGRP report.
3.2 Temporary Shielding The use of temporary shielding can be attributed with significant reductions in personnel radiation exposure for the SGRP. In the I
early stages of the project, extensive shielding of piping and components within the lower steam generator cubicles was performed to provide these work areas with minimum radiation exposure levels.
Where possible, this shielding has remained in place throughout the repair effort.
In addition to the initial shielding performed, specialized shield-ing techniques have been applied to further reduce the exposure levels associated with the task of installing the removed reactor coolant pipe sections. Section 3. 2 of Progress Report No. 3 for the SGRP described the use of specially fabricated shield "bags" to
PR4-6 SSGP reduce radiation streaming from the exposed pipe ends. During the actual welding of this pipe, lead "blankets" were also applied to the outside of the pipes to maintain exposure rates ALARA. Radia-tion survey data indicates that, on the average, exposure rates dSsociated with this task have been reduced by a factor of 5 through the application of shielding. When this reduction factor is applied to the actual exposure expended for installation of reactor coolant piping during the reporting period (about 115 manrem from Table 1),
a calculated exposure savings of approximately 460 manrem results.
3.3 Miscellaneous Valve Refurbishment During the removal phase of the project, a number of valves from the miscellaneous piping ( vents, drains, etc.) located in the lower steam generator cubicles were removed from the system. The removed valves were subsequently refurbished in preparation for reuse.
This refurbishment work consisted primarily of valve repacking and remachining of weld-preps, and was performed in the pipe refurbish-ment building outside the containment where exposure rates are much lower. General area exposure rates in the pipe refurbishment build-ing are approximately 0. 5 mR/hr as compared to average levels of 30 mR/hr within the lower steam generator cubicles. Additionally, detailed sketches of the miscellaneous piping systems were made to allow complete preparation of valve assemblies in the pipe refur-bishment building. In this way fit-up and weld-prep work inside the generator cubicles is minimized.
Since the miscellaneous piping systems contain radioactive contami-nation, the removed valves represent a source of radiation exposure during refurbishment and reinstallation. Some of these valves
PR4-7 SSGP exhibited contact exposure rates of greater than 1, 000 mR/hr. It was observed, however, that replacement of the valve packing generally reduced these radiation levels to 1/10 of the original value. Subsequent handling of the valves thus requires less ex-posure to personnel.
On page 9 of Table 1, the total exposure expended during the report-ing period for "Installation of Blowdown and Miscellaneous Piping" is approximately 48 manrem. Of this total, installation of miscellaneous piping (and valves) represents about 14 manrem. Con-sidering the exposure reductions discussed above, and their relative effects on the work performed, a conservative dose reduction factor of 10 is assumed for this task and can be used to calculate an ex-posure savings of about 126 manrem.
3.4 Training As was the case during the previous reporting period, the installa-tion of reactor coolant piping represented the major task performed during August and September with regard to occupational exposure.
While the shielding and decontamination of this piping have been effective in reducing the radiation exposure rates associated with this task, the use of mock-ups to train the workers involved has
'been successful in reducing exposure times. Extensive training in the activities to be performed is accomplished by "dry runs" in full scale piping mock-ups. Completion times have been noticeably reduced as the simulated activities are repeated to* maximize each worker's familiarity with the actual job situation. Quantifying th~ exposure savings which have been realized through the use of I
I
_J
PR4-8 SSGP mock-up training has not been attempted here, however, the inherent benefits of reducing exposure times for this major task continue to be of significant importance to the ALARA program.
3.5 General Techniques A number of more general procedures and practices which have been utilized throughout the repair effort to assure adequate control of occupational radiation exposure and to maintain this exposure ALARA are listed below:
(a) comprehensive Health Physics and training programs, (b) the "work package" concept for task preplanning and review, (c) the project photographic and video-tape documentation, (d) in-containment "rest area" utilization, and (e) periodic work area cleanup and debris removal.
Although quantitative assessments have not been performed for these "general" techniques, all have obvious value in contributing to the overall ALARA program for the steam generator replacement project.
PR4-9 SSGP 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General Radioactive liquid and gaseous effluents, and radioactively con-taminated solid waste generated during the steam generator replace-ment project are summarized in Table 2. A discuss'ion of each cate-gory is given below.
4.2 Airborne Releases Airborne releases for the reporting period originated primarily from continuous ventilation of the containment during the repair activities. This is necessary to maintain a negative pressure while the equipment hatch is open. The continuous flow is processed through appropriate filter banks to minimize the concentration of airborne particulates released to the environment_. Releases for August and September are seen in Table 2 to be consistent with those of the previous four months. No radioiodines or noble gases were detected and the particulates are comprised entirely of those nuclides with relatively long half-lives which would normally be expected at this stage of the repair ~ffort.
4.3 Liquid Releases The composition of radioactive liquid effluents released during the reporting period is relatively unchanged from that seen during the previous period. The major contributing nuclides are present at quantities which have remained consistent throughout the project.
It should be noted that the concurrent outage for Surry Unit No. 1 during August and September (as during previous months) may have contributed to the quantities of radioactive liquids released to the
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PR4-10 SSGP discharge canal; since a shared laundry facility is used for both units, and the disposal of laundry waste water continues to be the major source of these effluents.
4.4 Solid Radioactive Waste The disposal of contaminated paper waste, disposable protective clothing and contamination control materials, and, to a lesser degree, structural materials and components not intended for reuse continued to comprise the major portion of the solid radioactive waste generated during the reporting period.
PR4-ll SSGP
5.0 CONCLUSION
S The following general conclusions are based upon the information contained within this report.
(a) Although some variations can be seen when comparing the esti-mated vs. actual exposure expenditures for individual tasks, the total exposure (manrem) expended to date remains below the original estimate established prior to commencement of work.
This result, and the techniques described in Section 3 which haye played an important part in achieving it, confirm that the ALARA concept is being effectively implemented and applied to the steam generator replacement activities.
b) Radioactive liquid effluents have exceeded the total release estimate for activity presented on page 9.A.5-5 of the SGRP report. The total volume released to date is 97% of the estimated total. This indicates that liquid effluent concen-trations are somewhat higher than originally anticipated. It has also been noted that some contributions to the liquid re-leases reported have occurred due to the concurrent outage for Unit No. 1. Nevertheless, the total activity released to date continues to represent only a small fraction (less than 1%) of that normally expected during station operation.
(c) Airborne releases of radioactivity remain well below the esti-mates provided in the SGRP report on page 9.A.8-7 and are not anticipated to reach those estimates during the remainder of the project.
(d) Solid radioactive waste generated to date has exceeded the volume and activity estimates originally set forth on page 9.A.9-2 of the SGRP report. This has been attributed to the
PR4-12 SSGP increase in personnel assigned to the SGRP, and the expected subsequent generation of higher volumes of contaminated paper waste, disposable protective clothing and contamination control materials.
TABLE l PAGE 1 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 8/1/79-9/30/79 SURRY POWER STATION-UNIT NO. 2 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) {MANllOURS~ {MAN-REM~ {MAN-REM~ (MAN-REM) (I=IN PROGRESS)
- COMPLETED TASKS ONLY***
I Shutdown and Preparatory Activities 39,021 152,369 596.27 3.436 387.328 c II Removal Activities 57,422 189,927 559.6 0.878 698.300 c III Installation Activities 7,326 50,324 36.63 6.130 28.887 I IV Post Installation and Startup Activities 898 469 4.49 0 0.579 I v Steam Generator Storage Activities 300 3,535 35.0 0.004 4.880 c PROJECT TOTALS (Completed Tasks Only) 104,967 396,624 1,231.99 10.448 1,119.974
TABLE 1 PAGE 2 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 8/1/79-9/30/79 SURRY POWER STATION-UNIT NO. 2 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 (MANllOURS) (MANIIOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I=IN PROGRESS)
- ALL TASKS COMMENCED AS OF 9/30/79***
I Shutdown and Prepara-tory Activities 39,021 152,369 596.27 3.436 387.328 c II Removal Activities 57,422 189,927 559.6 0.878 698.300 c III Installation Activities 74,195 347,682 448.23 284.857 669.950 I IV Post Installation and Startup Activities 52,750 43,479 369.26 28.528 72. 261 I v Stearn Generator Storage Activ-ities 300 3,535 35.0 0.004 4.880 c PROJECT TOTALS (All Tasks) 223,688 736,992 2,008.36 317. 703 1,832.719
TABLE 1 PAGE -3 13
- OF PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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~ ~MANllOURS~ (MAN-REM) (MAN-REM~ (MAN-REM) (!=IN PROGRESS)
Erect Equipment Hatch Temporary Enclosure 264 1,073 0.4 0 0.459 c Prepare and Load Test Polar Crane 210 2,757 1.05 0.020 2.883 c Open Equipment Hatch 156 0.23 c (See Note l)
Defueling and Fuel Storage 585 3,437 11. 7 0 22 .124 c Install Reactor Vessel Cavity Cover 130 2,385 1.3 0 1.972 c Cutting of Pressurizer Cubicle Wall (See Note 2)
Installation of Jib Cranes 1,838 13,137 9 .19 0.026 14.693 c Disassemble Manipulator Crane 58 1,501 1. 74 0 2.416 c Install Steam Generator Transport System 572 7,366 2.86 0.945 12.682 c Removal of Biological Shield Wall 1,296 3,959 19.44 0 3.392 c Disassemble Shroud Cooling System 150 918 3.0 0.008 1.520 c
TABLE 1 PAGE 4 OF __!l_
PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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} {MANllOURS) {MAN-REM} (MAN-REM} {MAN-REM) (I=IN PROGRESS}
Cutting of Crane Wall at Hatch Opening 432 1,379 2.16 0 0.446 c Installation of Temporary Ventilation System 50 11,436 0.05 2.333 4.184 c Temporary Scaffolding 7,500 14,559 75 0 74.363 c Temporary Lighting and Power 5,200 6,609 26.25 0 0.563 c Cleanup and Dec on 9,000 17. 216 135 0 22.601 c Polar Crane Operator 1,500 1,368 4.5 0 2.319 c Shielding 3,600 21,930 270 0 143.493 c H.P., Q.A. 6,480 31,286 32.4 0 33.584 c ADDITIONAL TASKS Installation of Service Air System 2,491 0 0.670 c Work Platform Modification 5,111 0.086 0.170 c Removal of Reactor Coolant Pump Motors 1,357 0 4.621 c
TABLE l PAGE 5 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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) (MANI!OURS) (MAN-REM) (MAN-REM) (MAN-REM) (I=IN PROGRESS)
Protection of Contain-ment Components 1,094 0.018 4.054 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 0 5.657 N/A Craft Support and Security Escorts " 0 10.000 N/A Project Supervision and Administration 0 17.227 N/A Visitors and Inspectors " 0 1.235 N/A Subtotal Phase I (Completed Tasks Only) 39,021 152,369 596.27 3.436 387.328
TABLE 1 PAGE 6 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C~COHPLETE)
DESCRIPTION ~MANHOURS} (MANHOURS} (MAN-REM} ~MAN-REM} (MAN-REM) (I~IN PROGRESS)
Removal of Insulation (lower shell, RC Piping) 720 2,026 28.8 0 13.791 c Removal of Insulation (upper shell, mainsteam and radwater piping) 864 80 12 .96 0 1.364 c Removal of Miscellaneous Piping 72 5,424 1.8 0 59.337 c Set Up Steam Generator Girth Cut Equipment 1,152 224 28.8 0 0.229 c Cut and Remove Steam Generator Upper Shell 330 5,079 8.25 0 11.221 c Cutting of Reactor Coolant Piping 2,982 20,235 149. l 0.012 214.058 c Cutting of Mainsteam and Feedwater Piping 1,428 2,838 7.14 0 1.132 c Disassembly of Steam Generator Supports 792 9,986 15.84 0.858 47.071 c Removal of Moisture Separation Equipment 396 6,050 1.98 0 6.727 c Refurbish Steam Generator Upper Shell 9 ;246 21,746 46.23 0.008 19.819 c
TABLE l PAGE 7 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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} ~MANI IOU RS } (MAN-REM~ ~MAN-REM~ ~MAN-REM) (I=IN PROGRESS)
Removal of Steam Generator Level Instruments and Blow-down Piping 135 2,311 4.05 0 7 .671 c Removal of Steam Generator Lower Shell 1,575 3,859 31.5 0 29.875 c Temporary Scaffolding 7,500 11, 969 75.0 0 46.464 c Temporary Lighting and Power 5,250 6,071 26.25 0 5.910 c Cleanup and Decon 17 ,000 26,731 85.0 0 83. 718 c Polar Crane Operator 1,500 1,308 4.5 0 l.038 c H.P., Q.A. 6,480 32,999 32.4 0 50.960 c ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 30,991 0 53.897 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 0 4.858 N/A
TABLE l PAGE 8 OF 13 PERSONNEL RADIATION ExPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL ExPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=CmtPLETE)
DESCRIPTION (MANUOURS) (MANllOURS) (MAN-REM) (HAN-REM) (MAN-REM) (I=IN PROGRESS)
Craft Support and Security Not Reported 0 l.281 N/A Project Supervision and Administration 0 37.579 N/A Visitors and Inspectors II 0 0.300 N/A Subtotal Phase lI (Completed Tasks Only) 57,422 189,927 559.6 0.878 698.300
TABLE 1 PAGE 9 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III-INSTALLATION ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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 ~MANllOURS} ~MANllOURS} ~MAN-REM} (MAN-REM} (MAN-REH) (I=IN PROGRESS}
Steam Generator Lower Shell Installation 1,926 9,730 9.63 2.816 13 .826 c Installation of Reactor Coolant Piping 6,768 85,055 67.68 114 .544 307.791 I Steam Generator Girth Weld 5,400 40,594 27.0 3.314 15.061 c Installation of Main Steam Piping 3,735 11,615 18.68 12.609 14.085 I Installation of Feedwater Piping 2,700 7,253 13.5 3.136 3.462 I Installation of Blow-down and Miscellaneous Piping 1,782 14,250 17.82 48.100 51.690 I Install Steam Generator Level Instruments 2,592 3,105 12.96 2.751 2.772 I Installation of Insulation 11, 562 1,270 57.81 1.189 1.288 I Temporary Scaffolding 7,500 12,972 75.0 13.092 33.205 I Temporary Lighting
& Power 5,250 11,540 26.25 2.521 7.961 I
TABLE 1 !'AGE - 10 OF 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III-INSTALLATION ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE ( C;CO~IPLETE)
DESCRIPTION (MANHOURS) (MANIIOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I;IN PROGRESS)
Cleanup and Decon 17 ,000 47,621 85.0 31.983 77 .903 I Polar Crane Operator 1,500 2,337 4.5 0.142 1.060 I H.P., Q.A. 6,480 67,357 32.4 13.441 48.837 I ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 32,983 4.880 16.546 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 1.361 4.692 N/A II Craft Support and Security 0.628 1.079 N/A Project Supervision and Administration 28.273 68.392 N/A Visitors and Inspectors II 0.077 0.300 N/A Subtotal Phase III (Completed Tasks Only) 7,326 50,324 36.63 6.130 28.887
PAGE ll 13 OF -
TABLE l -
PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=COMPLETE)
TASK (!=IN PROGRESS)
DESCRIPTION (MANHOURS) ~MANHOURS} ~MAN-Rf,}!} (MAN-REM} (MAN-REM)
Install Biological I Shield Wall 3,240 347 16.2 0.008 0.107 Repair Crane Wall c Opening 473 326 2.37 0 0.392 Repair Pressurizer (See Note 2)
Cubicle Wall Install Steam Generator Recirculation and I Transfer System 9,000 33,140 90.0 17.192 60.172 Remove Reactor Cavity I Cover 130 30 0.65 0 0.030 Reassemble Manipulator I 1,176 452 23.25 0.259 0.304 Cr.ane Remove Steam Generator c Transport System 425 143 2.12 0 0.187 Reassemble Shroud I Cooling System 576 901 11.52 0.360 0.360 75.0 1.453 1.453 I Temporary Scaffolding 7,500 585 Temporary Lighting 26.25 0.281 0.281 I
& Power 5,250 473
PAGE OF TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ES TUIATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=COMPLETE)
DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REH) (MAN-REM) (MAN-REM) (I=IN PROGRESS}
Cleanup and Decon 17,000 2,249 85.0 3.554 3.554 I Polar Crane Operator 1,500 115 4.5 0.015 0.015 I H.P., Q.A. 6,480 3,1113 32.4 1.494 1.494 I ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 1,305 0.543 0.543 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 0.150 0.150 N/A Craft Support and Security II 0.068 0.068 N/A Project Supervision and Administration II 3.142 3.142 N/A Visitors and Inspectors 0.009 0.009 N/A Subtotal Phase IV (Completed Tasks Only) 898 469 4.49 0 0.579
TABLE 1 PAGE -1.L OF _u_
PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE V - STEAM GENERATOR STORAGE ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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 Storage Activities 300 3,535 35.0 0.004 4.880 c 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).
TABLE 2 PAGE _l_ OF 4 SURllY POWEii STATION STEAll GllNEnATOll Jlln'l.ACEllF.JIT PHOJECT YEAR: 1979 REPORT 01' RADIOACTIVE EFFl.UENTS -------
r_._L,,,_lfl_U_l_ll_R_E_L_E"'"A-S-ES-~----.--------i!r..of~~"'~_;:;~-"-~-s-_.R*_-~_..*_@_:c_~u_}_J_;.__~~----~---:~~--r-*c_~_1~_1~_~_:::_~_-::_.-.y.-_*:'."_~_="_=_~---~~_-::_-.:_:_:_-E1-:____:_:__:_:_~_:-_:_==_~~_:_.,._I_::_.*~_:_:_:_*.~_:~_:_,_*~...- -_~_:_.=__*-___--~__:_.~_:i~I-----*.._::_.~_-=_~~_-:-_~-_.:_:_:_:,~...':_::__:_~_-.=_:*_:__*~_**_.-~-
l<Joto11es Released MPC µCi/ml p 1-131 J x Ill- ,,-'--'-'"'--------e -*
l-132 B x 10-"
1 x 10- 6
- f<
I-133 2 x 10 5
*f< Ir
~
l-1Jl1 f<
1-us 4 x i*""o--*~,-----'----- Ir f< ~
Cs-lJl1 Co-57 9 x 10
--C-s---J-~J-7-------~z-;J.o=-s-
° 1, x"J.o-=.----------l--- -2~-
2.JOE-3 4.00E-3 7.UOE-4 'I 2.70E-3 2.JuE=-r- -
i
- ----,;----~------*------t1------~------
I I ~ ~
--c-o--~s*s~------9~x-To .. s.ooE-4 -i.ooE-Y-- 1 fi~=~~ r ~--rn~:-.---------11----+_-_~!-~-~-~-~-=-~---ll~-5-:~2~u=k,--=-~J--i_1--_-_-_-_-_-_-~~-=*~-----~~=::==-=--=--i'---_-_-_-
I
__________________~------
R II
- I
--~a-2~-- J X~..:ol~~--------------~----11-------l--~---ll------*--------~------J;------~------ii--------
- " u Cr-51 Fe-59 2 x 10- 3 5 x-10'3 __________ * ---w.--"
- u,-*~s 1 -~-10-r--- "
l.88E-7i 11. 56E-6 sb-124 2 x Jo-=:;------------ f< f<
- - - - - - --- 1:I Sb-125 1 ;*10=--* f<
L___
_ zi-6s ______ 1 *-;z*.~9~*,,------------ -
- J.60E-5 2.67E-5. . I
\I
!I I z1*-9s Mo-99 6 x 10->
4 ~--1-o---s*-----------11----*i------'o---~---*
f< ----... ~
f< ': i b Ru-10 J 8 ---;c-10---s- l.65E-6 9.BBE-7 I ~
!::-Xc-l JJ *a x 10-* f<
- I
~--Ag=JJJlm_ 1 x 10- 5 f< f< I
~ J x 10-s Nl-6J f<f<
-~* ** i j Fc-55 Ce-ll14 8 x 10-*
1 i: 10-s
r---11-..,,.-~,.,.--o--~----,----tt--------~---~-t---~-------jl~----.....;...------~-------
2.92E-5 f<
i I
3 f< f<
T.£..~~9m 3 >: 10 ---------lli-----~~-~~--~~~~~--11------11----'------t1------ti--------ti---------r------- i Cc-ll!_l_______~l_x-__JJJ:_5_ ___________,.. 4.25E-7 l.4BE-6 : I i Volume of 1~:_to-}i7 ls-c...,l,....ia-!"_-~--e........,C,...a_n_a-=1----+.--,----i---,..---,,==,.,,..---ti~.--.,,..,....-.---11-------
Liters !l.90E+:> l.95Ef6 I
I f<f<f< I
- Not De tee ted
- Sampl\! analysis results not yet recel.ved from service vendor.
Upon receipt, analysis dnta will be submitted os a supplement to th is report.
"'°'*Includes R:1dionct.ive Liq*uid Wnste generated during Dl outage
TABLE 2 PAGE 2 OF 4 SURRY POlllm STATIOH STEAi! GEllERATOR REPLACEMENT PROJECT llEl'OllT OF HADIOACTIVE EFFLUENTS - YEAR: _ _~l~9_,_7:!_9__
II. AIRBORNE RELEASES
~7;~r~;;c;-~--*n;1re-~;;;a:
-urrrTif~ -*. 1_-'i=~-;_*-_.r_~- =-~---~-,-_~-~- ~-i-.=.~_,_F_.i-_*-_*_-+*-___
... ~.....,*===~*~*--**-**-* . **-==** Eu,,_,*;,_,1,,,*~"';'--**;_-_*___- _--_ _ -
_~.:_:__ ~- - ~-~--_::_~--~----~-~-==~~---
- ==_-_ _:- _:~ =_: =.-~.~- ~*-----*-u--**-----+*---------il--_**
.._-_-_-_*_-+----_-_*_**_
.. -~-:~-.=-=-~.- .~_:._:.:_*:__:::==_::
____:_-~....=_. ~.-.- *~_:. _._._.-.=.:,~_*_ ~"-~-~~-~=--- **. *=~-*.r_=_=:.._______
~----_-_-_-_ -_--_--
4
____(.~..).__f..1Ll!.J;lllaJ:~.,_c_ _ _ _ _ _ _ _ _ _ _ !l----~--=---=-,,--:---lf-,-------ll---r-----~-,-*-~-11------11-------11------'1--------
1-------"'Ca.=lllt_ _ _ _ _ _ _ _ _ _ _ _ _ _ ll-----....;;-~~~~-'I----"'
Cs-1~3<J7c._ ______________ 11----+-~--___.
Cr-51 Co-SB
--~f-~,Q0--~6.ll~-------*----------li-----Jl-~~~--~--'-'C;.:*°'-'~-4-----.Jf-------t------1------4------1'-*------
1-~-~~Jl=.'.i~-*--*--*-----------~--~-__;:_~:.::___:__J-----~----~-1!1-------ll------!------'I------+--------
Fe-S9 1-132 1-115 (c) Gases Xe-133 Xe-})1m 1_ _ __..xe~--~l..,,3.~S--------------11---=---1--_.:_---1------1--------ll---l..---1------...J-----__J~----~-------
Kr-B5 m Kr-BS Kr-87 III SOIIILRAlllilAC'1'.lllRj~AS~'Iu'E,.__.Dul~S~PuOS~Awlu____ ~---1------~-----1------1---+---i------n.------l-------,1-------
(a) Total Amount Solle! Waste Packnged FT 3 B.70E+J l.66E+J (b) Estimated *fOtaf Activity Curies 4 .66E*l-O l.26E+O (c) Date of Shipment and Uarnwell, Barnwell, Disoosition s.c. s.c.
~*~~~~~~~-=~~"-==~==-&*11-~~'-"==9~-~1~2~-~19e==~~~~~~~~L~."=-=~~~"--'-~~~~.,......~~~~-*I~~-~~~
B-10-79 9-25-79 B-17-79
- Not Detected 8"21-79(3)
B-26-79(4)
TABLE 2 PAGE _3_ OF _i.:
SURRY POWER STATION STEAll mmrmATOR REPl..ACEIIBIIT PROJECT REPORT OF RADIOACTIVE EFFI.UENTS YEAR: _ _-'1""'9-'-7""'9_ _
~~- ,.ji>'Ru~__::, ::.: .Jffe -~ *.
- ;co;:=== .. ~=-
I. I.IQUID RELEASES ~mfilk\~ JUNE J~.
""'~~~* -
UJIITS Curies
____lo~j*es Released tlPC l!Cilml 1-131 ] x io- 7 2.76E-5 4.62E-4 6.2BE-S " .
l-1J2 e x !Q-6
- l-lJ] l 11 10-& * * " " "
I-134 2 x 10-~ * * " "
I-LJS Cs-134 4 x 10-'
9 x 10- 0 ]. 21E-J 2.2JE-]
- 2. 4JEJ-]
- 1. -1:::tl' *.J 2.4JE *J 2.20E-j Ca-137 2 x 10 **. 7:24E-J 5.90E-J 5. 82E-J ].97E-J 6 .wc;*J 2.90E-J
- Co-57 4 x 10-* 5. 54E-6 1.71E-6 9.00El-5 * * . lt.OOE-6 Co-Sil 9 x ro-* 2.J5E-2 l.15E-2 J. 47E-2 7.90E-3 6. Ioi!:-J 1. 60E-J
__f:o-60 J JLlll 1 5
2.0JE-2 9.09E-3 I. 72El-2 6.10&-J 1.lOE-2 ll.5UE-J tfn-54 1 x 10-
- 1. 28E-] J.42E'-4 7.32E-4 l.J1E-3 -r.:Jqr-q- 2. ZOE-4 tla-24 ] x 10-* * *
- I. HlD-5 " "
Ct*-51 2 x 10-l 6.4BE-4 T.-SOE-*l Z.UUI"*=>
5 x 10-*
5.55E-3 3.40E-3 "
-- Fc-59 * *
- a. BlE-5
- 5.60E-5 Sb-124 2 x 10-* 2. Iile--~ I.401H "
Sh-125 1 x 10-*
l.2JE-4
- l.6Jl:H ~.SOE-S . "
__ Zn-65 1 X 10- I l. llE-5. 4.06E-6 4. 70El-5 2 *. llltr:> 3.11!JE 6 I. 3!JE-5 Zr-95 6--x-Iu-* 1. 54El-4 7.0lE-6
- 5.20E-5 *
- tlo-99 5.92E-5
- Ru-103* e x .io-s * *
- l.16E-6 *
! Xe-133 a x io-* 9.42E-5 l.19E-4 * * " **
J x 10-5 2.66E-5 l.24E-5 * "4
AcllQm Ni-63 J x io-*
J. 46E-J 7, 22E-l 2.98&-J J,:!!,iE-1 14E-J 4.57E-3 Fe-55 ll K 10-* l.07E-2 6.lJE-2 T.25E-2 2.Tse--6
,.7.BBE-3 1. 61E-2 L21lE-3 5':511E-b Cc-144 ! !i l!r 5
- 9.59E-6 "
_'\'c-99m ] K 10-J fr 1. JSll-4 *Ii " " " .14t;-b 4.4IE-ii "
Ce-lH 2 x 10-s *
- j Valme of Licmid to Discharoe Canal Liters ---s:97tit' :J 7,1b1';-t-:J 9.60EF5 I.IIEHi l.15E-f-b 9.9JE+5
- imt Oetecterl
- Sanple analysis results not yet received from service l\lendor.
l4X>!l receipt, analysis data will be sli>mitted as a supplement to this report.
- Includes Radioactive Liq*uid Waste generated during 01 outage
TABLE 2 PAGE~ OF _4_
1 SUllllY l ow1m STt\TION STEt\11 r.mm1wron REl'Lt\CEMENT PROJECT REPORT OF llAnIOACTIVE Elll'LUENTS - YEAR : _ _-'1""9-'-7"""9_ _
II AIRDORNEI REIEt\SES
', I
~..:~-- *. -~.**~~~~ .._. -~~- =~~***~:._-~~<.~* ~::1 uiffir . .lWYAll- .,.Ji4fill1L- ~I~-, -~~- ..'...*lwt!L- ....W.Y~~ ,_._
~~iiaite1efil!C"~- * ----~ ,c;;;r;;-
---l~U*J.I..tli:ula!:J>"
... 1. 38E-6 1. lJJ..:-.)
C3-l lt.
- *
- 6. 37E-5 ll.90E-6 Co-58 8-0~E-~ t. l lE-5 3. 58El-5 1. 73E-5 Lo-60 4:.17E-5 ..Jt...QlE-5 4.14El-5 7. 79.El-5 3.33E-5 6.4JE-5
---r.3~
Mn.::'-!. * * * *
- w Fe-59
~) llaloi?ens HJ! 6.88E-6 l-132 * * * " "' "
I=.J..Jl * * * "w * "
I-J 1t. * "' * " "'* . "
- -*~~ * * * "
{c} Gase A .'
9.64~ 3.00Et-0 Ii Xe-lJJ
_ _ _ _&!.::.lJ11J1
- Ii Xc-))5 1. 94E+O *Ii * *
- Kr-!!5m
- Ii Ki--85 * * " 1t Kr-87
- li Ii ft ,"Ii 1t
_ _ _Kr-RR Ar-41 '! w T llL~-5.ULlIL..RAfl1.1JACID11LllASTR hl <: nn" * *
(a) Total t\moun t Solid Waste Packaged FT3 l.65E+3 l.11E+4 6.92E+J 6. 60EJl-3 9.30E+3 7.78E+3 (b} Estihmtc<I 'fotnI Activlty Curies 9. 91,E-l :J.I6Et-O 7:, /bi'IH i:!llBtO- ---Y:-ci3E+l 6.98E+O (c) Date of Sh.lpment nnd Barnwell, Dnrnwelli Barnwell, BanJWoll, D11rnwell, Barnwerr;--
Dlseosltlon S,G, <: (' s.c. s.c. s.c. s.c.
- z=..-:::-.;. -* ...
4-6-79=(4) :>-s-~
~ ~
3-6~79 3-17-79 -b-1-19 1-1 l':J 2-20-7 9 2-22-79 3-7-79 3-19-79 4-9-79 5-11-79 Ji-7-79(3) 7-10-79
- Not futected 3-8-79 3-'i!B-79 4-12-79 (2) 5-16-79 6-8-79 7-13-79 2-27-79
(+) iune date of shipments continued 3-13-79 3-28-79 4-14-79 5-19-79 6-13-79 7-16-79 2-28-79 6-25-79,6-26-79,6-27-79 3-13-79 3-29-79 5i.;23-79 (2) 6-14-79 7-18-79(2) 4-17-79 3-15-79 3-29-79 4-22-79 5-25-79 (2) 6-15-79(3) 7-20-79 5-2'}-79 6 79 7 79 5-30-79(2) 6-1.4-:-7'1 7-28-79
(+)