ML18139B515
| ML18139B515 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/30/1981 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139B514 | List: |
| References | |
| PROC-810630, NUDOCS 8109090141 | |
| Download: ML18139B515 (42) | |
Text
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- STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 1 FINAL REPORT*
(RADIOLOGICAL PROGRESS REPORT - NO. 5)
FOR THE PERIOD SEPTEMBER 14, 1980 THROUGH JUNE 30, 1981
- '/ 8109090141 8108-31~
PDR ADOCK 05000280!
p PDR::
,.1
1.0 INTRODUCTION
TABLE OF CONTENTS OCCUPATIONAL RADIATION EXPOSURES PAGE NO.
PRS-1 PRS-2 2.0 2.1 General PRS-2 2.2 Evaluation of Exposure Data PRS-2 2.3 Description and Format of Exposure Data PRS-3 2.4 Conclusions and Observations PRS-3 3.0 APPLICATION OF ALARA PRINCIPLES PRS-5 3 .1 General PRS-5 3.2 Initial Containment Cleanup PRS-5 3.3 Temporary Shielding PRS-6
- 3,4 Steam Generator Water Level PRS-8 3.5 Plasma-Arc Cutting Equipment PRS-8
- 3.6 3.7 3.8 Temporary Containments and Ventilation Mock-Up Training Videotape PRS-9 PRS-10 PRS-11 3.9 Reactor Coolant Piping PRS-11 3.10 General Techniques and Practices PRS-12 4,0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PRS-14 4.1 General PRS-14 4.2 Airborne Releases PRS-14 4.3 Liquid Releases PRS-14 4.4 Solid Radioactive Waste PRS-14 5.0 STEAM GENERATOR STORAGE BUILDING SURVEILLANCE PRS-16
6.0 CONCLUSION
S PRS-17 i
- l. I TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents*
Table 2A - Effluent Release and Solid Waste Comparison Summary Table 2B - Liquid Effluent Isotopic Distributions Table 2C - Gaseous Effluent Isotopic Distributions ii
~I PRS-1 SSGP
- 1. 0 INTRODUCTION
- The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No.
June 30, 1, commenced on September 14, 1980 and was completed on 1981. This Final Progress Report contains information on the radiological effects of the SGRP, and on the measures taken to maintain these effects "as low as reasonably achievable" (ALARA).
Much of the information presented has been obtained from earlier radiological progress reports submitted periodically during the repair program.
The following report sections provide an assessment of the occupa-tional radiation exposure expended, the dose reduction techniques employed and their effectiveness, and the radioactive effluents and solid waste generated during the repair program. An assessment of the surveillance activities associated with onsite storage of the old steam generator lower assemblies is also provided.
This final report has been prepared pursuant to the license condi-tions issued under Amendment No. 47 to the operating license for Surry, Unit No. 1 and, as such, completes and fully satisfies the requirements set forth in those conditions.
PRS-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 Table 5.3-1 of the SGRP Report, thereby permitting valid comparisons between estimated and actual expenditures. This section discusses the implementation of that program and provides an evaluation of the occupational exposure information compiled during the repair effort.
2.2 Evaluation of Exposure Data The exposure assessment program referred to above was 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-di tu res. The worker task data was standardized to 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 facilitated the process of compiling an accurate breakdown of the collective exposure ex-pended on the many tasks performed.
i '
PRS-3 SSGP 2.3 Description and Fonnat of Exposure Data
- Table 1 presents a summary of the occupational radiation exposure expended during the repair effort, the exposure related labor ex-penditures, and the original estimated expenditures. The following comments are provided for clarification and should be considered when reviewing the data presented.
(a) Additional tasks perfonned during the repair program 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-fonning functions not directly attributable to any specific, pre-defined task have been listed separately. Expenditures reported for these "Additional Tasks" and "Unassigned Person-nel Categories" were allocated to a particular phase based upon the major activities being performed at the time they were incurred.
(b) For each phase (except Phase V), separate subtotals are
- provided for: (i) the "pre-defined tasks" and (ii) the "addi-tional
- tasks and unassigned personnel categories". Page 1 of Table 1 provides a summary of the "pre-defined tasks" subtotals for each phase and a summation of the "additional tasks and unassigned personnel categories" subtotals for all phases. The Project Totals are also shown on Page 1 of the table.
2.4 Conclusions and Observations (a) The total occupational radiation exposure expended during the repair program for Unit No. 1 was approximately 15%, or 309 manrem, below the exposure estimate of 2,067 manrem.
(b) During the repair effort, no worker assigned to the SGRP re-ceived radiation exposure in excess of the federal standards specified in 10CFR20 .
\,
PRS-4 SSGP (c) The actual labor expenditures (manhours) reported in Table 1
- exceed, in most cases, the estimates made during the project planning phase.
peripheral and This is largely attributed to the fact that support activities performed in conjunction with a specific task have been included in the assessment of actual expenditures. The labor estimates developed prior to commencement of work were directed primarily toward providing a basis for evaluating the task exposure estimates and were not intended to consider or anticipate these additional activ-ities .
\,
PRS-5 SSGP 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General This section summarizes the specific techniques and practices which were employed during the repair effort in order to maintain occupa-tional exposures to radiation "as low as reasonably achievable" (ALARA). Where the available data permits, the following evalua-tions include a quantitative assessment of the manrem savings which can be attributed to the technique used. Additional information on these techniques and how they relate to the overall steam generator replacement activities can be found in the SGRP Report.
3.2 Initial Containment Cleanup After shutdown and the removal of all fuel from the reactor, a general cleaning of the containment interior was performed to re-move loose radioactive contamination in the work areas and thereby reduce the potential for airborne contamination during subsequent activities. Additional cleaning and debris removal was performed after the biological shield walls and steam generator insulation were removed. The exposure received by personnel involved in these initial cleaning activities totaled approximately 58 manrem. The benefit, in terms of manrem savings, is difficult to quantify, how-ever, the following observations give some indication as to the favorable results obtained.
(a) The use of respiratory protection devices, with their inherent degrading effect on worker efficiency, was rarely required, except as a localized precautionary measure for specific cut-ting and grinding activities.
(b) An *extensive whole body counting program, to monitor workers for internal radioactivity, and the use of "Friskers" and portal monitors, to detect radiation on body surfaces, identi-fied no instances of significant internal or external personnel contamination during the repair program.
PRS-6 SSGP The worker's ability to perform tasks more efficiently, and thus
- complete them more quickly, undoubtedly resulted in a reduction of the time spent in radiation areas.
workers involved even a Considering the large number of small reduction in individual exposure times can produce significant savings in total manrem. The initial cleanup effort and the maintenance of good radiological working conditions are thus considered successful ALARA techniques.
3.3 Temporary Shielding The use of temporary shielding can be attributed with significant reductions in personnel radiation exposure for the SGRP. A separate work package was devoted to the design and installation of shielding and frequent evaluations were performed to identify improved methods and new applications.
The lower steam generator cubicles received the most extensive application of shielding during the repair effort and thus the work performed in these areas benefitted most directly from its use.
Piping and components located in the cubicles were shielded to achieve minimum exposure levels prior to the start of cutting and removal activities. After cutting of the reactor coolant piping, shield plugs were installed in the steam generator and pipe openings to reduce radiation "streaming". During the installation phase, additional shielding of the exposed reactor coolant pipe ends was performed, by placing specially fabricated bags containing lead beads inside the pipe and lead "blankets" on the outside surfaces.
The removal and installation of miscellaneous piping located within the cubicles also received a significant shielding effort utilizing lead blankets and sheet lead "curtains".
Detailed radiation surveys were performed frequently and have pro-vided a basis for evaluating the effectiveness of temporary shield-ing in achieving net reductions in personnel exposure. Survey data obtained prior to and after shielding installation permits the cal-culation of average dose rate reduction factors for appropriate tasks, and thereby an assessment of manrem savings. Three tasks
PR5-7 SSGP involving significant personnel exposure have been considered in this assessment.
(a) Cutting and removal of reactor coolant piping is reported in Table 1 as requiring the expenditure of about 77 manrem. Con-tact exposure rate measurements obtained during surveys has shown that an average dose rate reduction factor of 6 was achieved by shielding of this pipe. Using this factor and the actual exposure value for the task, a postulated expenditure of about 462 manrem would have been required to complete the task without the benefit of shielding. An assumed savings of 385 manrem can thus be credited.
(b) The removal of miscellaneous piping located in the steam gene-rator cubicles accounted for the expenditure of approximately 14 manrem. Shielding applied_to this pipe provide~ an average dose rate reduction factor of 5. Thus, without shielding 70 manrem would have been required to complete the task. A savings of 56 manrem is credited *
- (c) The installation of reactor coolant piping involved several major activities inside the generator cubicles. Included were pipe end refurbishment and fit-up and welding of new coolant pipe sections. In Table 1, the installation of reactor cool-ant piping is reported to have required a total expenditure of 234 manrem. Survey data indicates that shielding performed for these*activities was effective in reducing dose rates by a factor of 6, and thus resulted in a savings of 1,170 manrern.
Totaling the exposure savings calculated for the above three tasks results in an overall savings of about 1,611 manrem attributable to the use of temporary shielding. The exposure "cost" incurred during installation of shielding is listed in Table 1 as approximately 64 manrem. A comparison of these "benefits" and "costs" provides a clear indication of the value of this technique in maintaining occu-pational exposures ALARA.
t, PRS-8 SSGP 3.4 Steam Generator Water Level In the early stages of the SGRP, the water in the secondary system was maintained at a level.covering the steam generator tube bundles in order to fully utilize its shielding quality. The high water level was maintained until the lower portion of the steam generator was ready to be removed from the containment, at which time it was drained to remove the extra weight. The shielding effect of this water has historically provided an approximate 10 to 1 dose rate reduction for the area of the steam generator above the tubesheet.
This reduction factor was substantiated by actual survey results obtained during the removal phase and can be used to assess the effectiveness of this technique for several appropriate tasks.
(1) Removal of Insulation (upper shell, mainsteam and feedwater piping)
(2) Cut and Remove Steam Generator Upper Shell (3) Cutting of Mainsteam and Feedwater Piping (4) Disassembly of Steam Generator Supports (5) Removal of Steam Generator Level Instruments and Blowdown Piping.
All of these tasks were performed in areas where the shielding effect of the steam generator water was beneficial. The total exposure received for these five tasks was approximately 23 manrem.
The observed dose reduction factor of 10 thus translates into a postulated exposure savings of 207 manrem. Since practically no exposure "costs" were required to utilize this technique, its contribution to the ALARA program is obvious.
3.5 Plasma-Arc Cutting Equipment In order to remove the steam generator lower shells from the con-tainment, sections of the reactor coolant piping were cut and removed. A plasma-arc cutting torch was chosen as the means for performing these cuts. Plasma-arc has high cutting speed and pro-duces good cut quality for pipe reinstallation. The high cutting rate was a primary factor in this choice since faster cutting means
PRS-9 SSGP reduced exposure times. During the evaluation of this task, alter-nate 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 actual use, most of the reactor coolant pipe cuts were performed in approximately 20 minutes with the plasma-arc torch. Equipment set-up times were estimated to be about the same for all methods considered, since all would require special track mounting to maintain the close tolerances necessary for fit-up of new reactor coolant pipe.
The exposure savings attributable to the use of plasma-arc equipment could not be assessed, since the total manrem reported for the cut-ting of reactor coolant piping include significant contributions from equipment set-up and pipe removal. However, this technique has proven valuable in reducing exposure times and its use is consistent with the ALARA committment.
As a result of improvements made in the plasma arc cutting equip-
- ment prior to the Unit 1 outage, the cutting of the reactor coolant piping was accomplished with a total expenditure of 77 manrem. This compares to the Unit 2 outage in which 214 manrem was expended for this operation.
3.6 Temporary Containments and Ventilation To a large degree, the initial containment cleanup and decontamina-tion minimized the need for extensive use of temporary containments such as tents and glove boxes to control the spread of contamina-tion. However, in areas where significant cutting and grinding work was performed on highly contaminated piping and components, temporary containments were constructed and effectively utilized.
The most significant application of this technique was made in the lower steam generator cubicles, where the removal of reactor cool-
- ant and miscellaneous piping was performed.
lower cubicle for each steam generator was In Unit No. 1, the totally enclosed to
L, PRS-10 SSGP transform the entire room into a single contairnnent. Portable ventilation units. continuously withdrew air from these enclosures through appropriate filters whenever cutting or grinding operations were in progress. Personnel working inside the cubicles were required to wear respiratory protection equipment during these operations, and until the ventilation flow effectively reduced the airborne radioactivity to acceptable levels.
Additional tent enclosures were constructed in various locations to provide controlled work areas for pipe cutting, component refur-bishment and equipment decontamination. Portable, filtered venti-lation was provided to these enclosures as appropriate.
The benefits observed for these ALARA techniques were threefold.
(a) The use of small glove boxes for individual pipe cuts was eliminated, These devices required considerable time and exposure to ins tall and remove, and during the Unit 2 SGRP were found in many cases to be counter-productive to ALARA due
- (b) to this fact.
The use of temporary containments, especially as applied to the lower steam generator cubicles, largely eliminated delays and interference with work being performed in adjacent areas while cutting and grinding of contaminated piping was in pro-gress.
(c) The overall potential for airborne contamination and problems associated with contamination control was minimized by effec-tive use of temporary containments and portable ventilation.
3.7 Mock-up Training The installation of reactor coolant piping represented the most significant task performed during the repair effort with regard to occupational exposure. While the shielding techniques described earlier were effective in reducing the radiation exposure rates
PRS-11 SSGP associated with this task, the use of mock-ups to train the workers involved can be credited with providing reductions in exposure times. Welders, pipe-fitters, riggers and laborers all received extensive training in the activities to be perfonned by "dry runs" in full scale piping mock-ups. Completion times were noticeably reduced as the simulated activities were repeated to maximize each worker's familiarity with the actual job situation. Quantifying the exposure savings which have been realized through the use of mock-up training has not been attempted here, however, the inherent benefits of reducing exposure times for this major task were of significant importance to the ALARA program.
3.8 Videotape As part of the Unit 2 outage a consultant was retained to videotape and take 35mm slides of the major activities during the project.
This documentation was then edited into a one hour videotape which was used as a training aid to familiarize workers with the steam generator replacement program . The actual exposure savings which
- can be attributed to use of this videotape are difficult to quan-tify, however, the desired effect was to familiarize workers with the job and the environment in which it was to be performed, there-by eliminating a period of familiarization inside the contairnnent.
3.9 Reactor Coolant Piping For the Unit 2 SGRP, the old reactor coolant pipe sections were re-used. In Unit 1, new reactor coolant pipe elbows were installed.
This eliminated the task of decontaminating reactor coolant pipe sections, which required the expenditure of approximately 42 man-rem during the Unit 2 repair effort. Additionally, during the Unit 2 outage, three sections of reactor coolant piping were removed from each loop. Based on experience gained in Unit 2, it was deter-mined that removal of only two pieces of pipe would still allow an acceptable fitup to be achieved during reinstallation. This fact, in addition to the acquired familiarity with reinstallation of reactor coolant piping, is estimated to account for an additional savings of 95 manrem.
PRS-12 SSGP 3.10 General Techniques and Practices
- In addition to thus far, practices the specific dose reduction techniques described it is important to note the more general procedures and which were implemented prior to and during the repair effort to assure adequate control of occupational radiation ex-posure and to maintain this exposure ALARA. A brief description of each is given below.
(a) A comprehensive Heal th Physics program was implemented to provide adequate control and surveillance of the radiation hazards associated with each task. This program included the use of Radiation Work Permits (RWP' s) to familiarize workers with the specific radiological hazards involved and proper protective measures to be taken in the performance of their work. The successful implementation of this program is evi-deuced by the excellent radiation protection record which was achieved.
(b) An extensive training program was conducted to provide ade-quate instruction in the biological effects of radiation exposure, radiation protection practices and applicable federal regulations to all personnel involved in the steam generator replacement activities. Training for specific tasks, using mock-ups, photographs or "dry runs" was conducted where appropriate.
(c) The use of discrete "Work Packages" provided a mechanism to assure adequate preplanning and review of specific tasks, with special emphasis on minimizing radiation exposures to the personnel involved.
(d) Spec'ial tools and equipment, designed to minimize personnel exposure times by increasing worker efficiency and providing remote handling capability were utilized where practicable .
PRS-13 SSGP
( e) A consultant was retained to compile an extensive photographic
- and video-tape documentary of the entire steam generator re-placement project for Unit No. 2. Components, equipment and work areas involved in the major tasks were photographed in detail to record significant events as the tasks progressed from start to completion. Video-tapes were used to record actual operations where complex procedures or equipment was used, or where the activity was repetitive in nature. This documentation was of significant benefit in training and retraining of personnel for the Unit No. 1 Steam Generator Replacement Project.
(f) General work area cleanup and debris removal was performed periodically to avoid buildups and maintain good radiological working conditions. Decontamination of tools, equipment and components was also performed when necessary to facilitate handling and transfer. These efforts resulted in cleaner and safer work areas and minimized the potential for radioactive airborne contamination throughout the repair effort.
(g) Early in the project, "rest areas" were designated inside the containment to accommodate workers during idle periods. The rest areas were located where exposure levels were minimum (less than 5 mR/hour) and were well posted for identification.
Effective utilization of rest areas was continually emphasized to workers in order to minimize unnecessary exposure.
Although quantitative assessments could not be performed for these "general" techniques, all have been of significant value in contri-buting to the overall ALARA program for the steam generator replace-ment project .
PRS-14 SSGP
- 4. 0 RADIOACTIVE EFFLUENTS AND SOLID WASTE
- 4.1 General Radioactive liquid and gaseous effluents, and radioactively con-taminated solid wastes generated during the SGRP for Unit No. 1 are summarized in Table 2. A description of each category is given below.
4.2 Airborne Releases Airborne releases during the repair effort originated primarily from the initial purging of containment following shutdown, and continuous ventilation thereafter. This was necessary to maintain a negative pressure while the equipment hatch was open. These re-leases were processed through appropriate filter banks to minimize the concentration of airborne particulates released to the environ-ment. The relative isotopic distributions observed for airborne releases is presented in Table 2C.
4.3 Liquid Releases The major contributor to liquid effluent releases attributed to the SGRP was the disposal of laundry waste water. The activities and relative distributions of the major isotopes released in liquid effluents is presented in Table 2B.
4.4 Solid Radioactive Waste The solid radioactive waste generated during the repair effort consisted of: (i) contaminated insulation, structural materials, and components not intended for reuse, (ii) solidified liquids used for decontamination, and (iii) contaminated paper waste, disposable protective clothing and contamination control materials.
PRS-15 SSGP 5.0 STEAM GENERATOR STORAGE BUILDING SURVEILLANCE The Steam Generator Storage Building was reopened in November of 1980 to receive the steam generator lower assemblies removed from Unit No. 1. The building was subsequently closed and resealed, and a periodic surveillance program was resumed. Average contact expo-sure rates measured on the outside of the building are less than 0.1 mR/hr, as anticipated, and the building HEPA filters continue to show no detectable radioactivity. It is apparent, however, that some pathway for water intrusion into the building still exists; as shown by periodic checks of the collection sump level. Additional sealing work is planned to correct this condition .
PRS-16 SSGP
6.0 CONCLUSION
S The following general conclusions have been made based on the information contained within this report.
(a) The total exposure (manrem) expended during the repair effort on Unit 1 was significantly less than the original estimate established prior to the project, and represents a consider-able exposure savings when compared to the Unit No. 2 total.
The ALARA techniques described in Section 3, and the benefit of prior experience gained during the Unit No. 2 SGRP are attributable as the major factors in this success.
b) Radioactive liquid effluents were below the total release estimate presented on page 9.A.5-5 of the SGRP Report and, as expected, were less than 1% of that normally encountered dur-.
ing station operation.
(c) Radioactive gaseous effluents released during the repair pro-gram were comparable to, but less than the estimates esta-blished in the SGRP Report on page 9.A.8-7. The reported noble gas releases occurred as a normal result of the defueling operation. Radioiodine releases were comparable to the esti-mated value and gradually decreased to undetectable quantities due to their short half-lives. Radioactive particulate and tritium releases were lower than but comparable to the esti-mated quantities.
(d) Solid radioactive waste generation for the Unit No. 1 repair program exceeded the volume and activity estimates set forth on page 9.A.9-2 of the SGRP Report, as was the case for Unit No. 2.
(e) Surveillance data obtained thus_ far indicates the following with respect to onsite storage of the old steam generator lower assemblies .
PRS-17 SSGP (i) Radiation levels measured at the outside wall of the storage building are less than 0.1 mR/hr on contact.
This is less than the estimated level presented on page 9 .A. 16-3 of the SGRP Report. Therefore, the resulting radiation level at the site boundary will be less than 0.0001 mR/hr, as anticipated.
(ii) Samples of the building HEPA filters have contained no detectable radioactive particulates; an indication that cleari and stable airborne conditions exist within the building.
(iii) Water intrusion into the building is still occurring and additional sealing is necessary to correct this situation .
TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
Page 1 of 13 STEAM GENERATOR REPLACEMENT ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED PHASE DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
I Shutdown and Preparatory 39,021 45,424 596.27 194.786 Activities II Removal Activities 57,422 142,783 559.6 396.511 III Installation Activities 74,195 402,013 448.23 811.531 IV Post Installation and 62,650 91,518 427.54 150.589 Startup Activities V Steam Generator Storage 300 937 35.0 8.079 Activities SUBTOTAL 233,588 682,675 2,066.64 1,561.496 Additional Tasks and Unassigned Personnel ------ 109,452 ------- 197 .319 Categories PROJECT TOTALS 233,588 792,127 2,066.64 1,758.815
- e Page 2 of 13 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Erect Equipment Hatch* 264 ------ 0.4 -------
Temporary Exposure Prepare and Load Test 210 463 1.05 1.285 Polar Crane Open Equipment Hatch** 156 ------ o*. 23 -------
Defueling and Fuel Storage 585 2,863 11. 7 23.503 Install Reactor Vessel 130 753 1. 3 1. 915 Cavity Cover Installation of Jib Cranes 1,838 3,492 9.19 5.479 Disassemble Manipulato; Crane 58 629 1. 74 1.533 Install Steam Generator 572 3,948 2.86 6.953 Transport System Removal of Biological 1,296 916 19.44 2.298 Shield Wall Disassemble Shroud Cooling 150 601 3.0 1. 228 System
Page 3 of 13 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMA,TED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Cutting of Crane Wall at 432 586 2.16 1. 208 Hatch Opening Installation of Temporary so 106 0.05 0.053 Ventilation System Temporary Scaffolding 7,500 4,846 75 14.786 Temporary Lighting 5,200 2,174 26.25 2.162 and Power Cleanup and Decon 9,000 14,920 135 57.975 Polar Crane Operator 1,500 198 4.5 0.137 Shielding 3,600 2,045 270 64.315 H.P., Q.A. 6,480 6,884 32.4 9.956 PHASE I SUBTOTAL 39,021 45,424 596. 27 194.786
- TABLE l Page 4 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. l ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
ADDITIONAL TASKS Installation of Service ------ 627 ------- 2.198 Air System Work Platform ------ 1,939 ------- 0.752 Modification Protection of Containment ------ 1,289 ------- 6.158 Components UNASSIGNED PERSONNEL CATEGORIES Project Supervision ------ Not Reported ------- 8.471 and Administration SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) ------ 3,855 ------- 17.579 PHASE I PROJECT TOTAL 39,021 49,279 596.27 212.365
- *TABLE 1 Page 5 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Removal of Insulation 720 1,647 28.8 14.000 (lower shell, RC Piping)
Removal of Insulation (upper shell, 864 959 12.96 5.354 mainsteam and feedwater piping)
Removal of Miscellaneous 72 1,288 1.8 13. 896 Piping Set Up Steam Generator 1,152 90 28.8 0.208 Girth Cut Equipment Cut and Remove Steam 330 5,529 8.25 9.173 Generator Upper Shell Cut ting of Reactor 2,982 7,181 149.1 76.682 Coolant Piping Cutting of Mainsteam and 1,428 1,399 7.14 2.391 Feedwater Piping Disassembly of Steam 792 6,988 15.84 55.120 Generator Supports Removal of Moisture 396 5,333 1. 98 9.402 Separation Equipment Refurbish Steam Generator 9,246 12,990 46.23 10.884 Upper Shell
- *TABLE 1 Page 6 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Removal of Steam Generator Level 135 1,472 4.05 6.389 Instruments and Blowdown Piping Removal of Steam Generator 1,575 4,341 31. 5 22.870 Lower Shell Temporary Scaffolding 7,500 13,611 75.0 40.919 Temporary Lighting 5,250 5,356 26.25 4.451 and Power Cleanup and Decou 17,000 44,732 85.0 88.604 Polar Crane Operator 1,500 2,365 4.5 2.428 H.P., q;A. 6,480 27,502 32.4 33.740 PHASE II SUBTOTAL 57,422 142,783 559.6 396.511 ADDITIONAL TASKS Material Handling, Equipment 24,484 35.868 Maintenance, and Miscellaneous Construction Activities
- TABLE 1 Page 7 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIV,ITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
UNASSIGNED PERSONNEL CATEGORIES Project Supervision ------ Not Reported ------- 19.379 and Administration SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) ------ 24,484 ------- 55.247 PHASE II PROJECT TOTAL 57,422 167,267 559.6 451. 758
- TABLE 1 Page 8 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED
\ TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Steam Generator Lower 1,926 12,250 9.63 25.888 Shell Installation Installation of Reactor 6,768 31,365 67.68 233. 771 Coolant Piping Steam Generator 5,400 15,791 27.0 12.341 Girth Weld Installation of Main 3,735 7,036 18.68 3.335 Steam Piping Installation of Feedwater 2,700 6,418 13.5 2.997 Piping Installation of Blowdown and 1,782 16,051 17.82 93.686 Miscellaneous Piping Install Steam Generator 2,592 8,297 12.96 10.525 Level Instruments I*
Installation of 11,562 1,024 5 7. 81 6.531 Insulation Temporary Scaffolding 7,500 28,757 75.0 91.674 Temporary Lighting 5,250 11,805 26.25 6.477 and Power
- TABLE 1 Page 9 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Cleanup and Decou 17,000 172,542 85.0 221. 466 Polar Crane Operator 1,500 9,225 4.5 4.863 H.P., Q.A. 6,480 81,452 32.4 97 .977 PHASE III SUBTOTAL 74,195 402,013 448.23 811.531 ADDITIONAL TASKS Material Handling, Equipment ------ 67,539 ------- 70.694 Maintenance, and Miscellaneous Construction Activities UNASSIGNED PERSONNEL CATEGORIES Project Supervision ------ Not Reported ------- 33.876 and Administration SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) ------ 67,539 ------- 104.570 PHASE III PROJECT TOTAL 74,195 469,552 448.23 916.101
- TABLE 1 Page 10 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Install Biological 3,240 2,772 16.2 4.822 Shield Wall Repair Crane Wall 473 95 2.37 0.080
.Opening Install Steam Generator 9,000 12,771 90.0 33.756 Recirculation and Transfer System Remove Reactor Cavity 130 161 0.65 0.375 Cover Install Reactor Cavity 240 1,665 1. 2 2. 692 Coaming Reassemble Manipulator 1,176 1,572 23.25 1. 783 Crane Remove Steam Generator 425 47 2.12 0.014 Transport System Reassemble Shroud 576 2,610 11. 52 3.055 Cooling System Hydrostatic Tests 75 2,923 0. 38 7.447 Refueling 585 600 11. 7 2.158
- TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
Page 11 of 13 PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Temporary Scaffolding - 7,500 5,937 75.0 17.956 Temporary Lighting 5,250 2,379 26.25 1.302 and Power Cleanup and Decon 17,000 36,104 85.0 41. 078 Polar Crane Operator 1,500 1,845 4.5 0.918 Painting 9,000 3,478 45.0 14.869 H.P., Q.A. 6,480 16,559 32.4 18.284 PHASE IV SUBTOTAL 62,650 91,518 427 .54 150.589 ADDITIONAL TASKS Material Handling, Equipment ------ 13,574 ------- 13.007 Maintenance, and Miscellaneous Construction Activities
- TABLE 1 Page 12 of 13 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
UNASSIGNED PERSONNEL CATEGORIES Project Supervision ------ Not Reported ------- 6.916 and Administration SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) ------ 13,574 ------- 19.923 PHASE IV PROJECT TOTAL 62,650 105,092 427. 54 170.512
- TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
Page 13 of 13 PHASE V - STEAM GENERATOR STORAGE ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Steam Generator Storage 300 937 35.0 8.079 Activities TABLE NOTATION
- The Equipment Hatch Temporary Enclosure used for the Unit No. 1 SGRP was the same structure used for Unit No. 2 previously. Thus, no fabrication was involved and erection required only lifting and placement. Insignificant labor and exposure were expended for this task.
- 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.
- TABLE 2 SURRY POWER STATION PAGE 1 of 6
- STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1980 September October Novemher "----',pr
~. UNt°TS I. LIQUID RELEASES Curies Isotooe: Released MPC uci/ml
- I-131 3 X 10-1 S.96E-5 I-132 8 X lQ-6
/,. Q *:ii;*. ~ ? ?~R-"l I-133 1 X 10- 6
- 1. 73E-6 1.32E-5 3.47E-7 I-134 2 X 10-*
I-135 4 X 10-6 * *
- Cs-134 9 X 10- 0 3.0lE-4 8.32E-4
- 1.89E-6 3.57E-7 Co.-5!1 g X 10-* S.73E-4 ':\ /llR. ':\ 1.36E-2 !J.b0~-4 Co-bU 3 X 10- 0 1.lOE-3 'i 72F-3 1.BlE-2 3.48E-3 Mn-54 1 X 10-* 3.36E-5 1 llE-4 2,78E-3 4.45E-5 Na-24 3 X 10- 0
- 1.17E-3 6.29E-3 '*""
Cr-51 2 X 10- 3 1.99E-4 4.87E-4 1.14E-4
- Fe-59 Nb-95 5 X lQ- 5_
- 1.llE-5 l V 10-" S.68E-S 3.66E-5 1 21R .<;
Sb-124 , 1.20E-6 -*
Sb-125 2 X ]Q- *
- 7.SOE-7 1.44E-6 Zn-bS l V 10-"
- 3.86E-5 2.60E-6 Zr-95 l x l 0-"
6 X 10-
/,. X 10- 5 Mo-99 * * *
- Ru-103 8 X 10- 5
- 1.89E-6 *
- Xe-133 3 X 10- b 8.66E-5 4.74E-4 1.BSE-2 3.68E-6 Xe-135 Xe-133m 3 X 10-*
- 7.48E-5 1.lSE-5 2.41E-3
- 3 X 10-6 * *
- Ar-41 3 X 10-6 8.38E-7 *
- Ag-HOm 3 X 10- 5
- ~
Ni-b3 3 X 10- 5 *
- 1 ..lSE-3 1:ooE-3 4.0lE-5 l.41E-3 Fe-55 8 X 10-* 1.16E-4 1.12E-2 *
- Ce-144 1 X 10-6 * *
- Tc-99m 3 X 10-'
- 1. 77E-7 "
Ce-141 9 X 10- 0
- 9.0BE-7 *
- Volume of Liquid to Discharge Canal IT~~--- 6.70E+4 S.89E+S 1.16E+6 4.76E+5
- Not Detected
TABT.E 2 SURRY POWER STATTON PAGE 2 of_6__
STEAM GEN°ERJ\TOR REPJ.ACEMENT PRO.JECT REPORT OF RADIOACTIVE --- IWFLlfENTS
- ---- YEAR: 1980 II. AIRBORNE RELEASES ';* ...... _......_ ~.--=-~- - - - --**=-= =~~-,-~ --~--:*-~- ~--
UNITS September October November 'December u--..-s .
Isotopes Released: -* -~~---,-*--**-**.:!.-.. - ciia~~= -=-:-~--..-.. ==-~-=-=*- **--- .. *----~ -
(a) Particulates Cs-134 3.12E-6 1 22E-6 2.73E-6 Cs-137 9.07E-6 1. 76E-5_
j,66E-5
- 5.97E-5 6.27E-5
-~.:.54 I Fe-59 Cs-138 *
- 1.()lE-4 Rb-88 * *
- * 'i ?l.F-'i *
~b) Halogens 1-1,31 l.78E-3 7.90E-4 l.74E-5
- - -- l6....12E::..l.
I-132 4.73E-6
- l.31E-6 1- I-133 2.12E-6 2.31E-5 4.03E-5 I I-lJ{! * * *
- T-11'i
(!;;) !,a1,e1, Xe-133 4.44E+2 5.26E+l
- 5.22EO Xe-133m 7.89EO Xe-135 I Kr-85m 3.21E-1 * *
- Kr-85 * * *
- Kr-87 * * *
- Kr-88 *
- 1<
Ar-41 - * * "
Xe-131m " "
\ H-3
- 7 .OBE-1
- 2,lSE-1 6.97E-2 5.62E-2 I*
I I .. ----- - - - --
I ----*--- - - - *----~I r--
- -- . -. *-. . ___ .__ ., . . . - - . - .. - - _, *- -*- *.. _- *-. -* ***- -- ~ ==-=--;-.
~ ~~,.- - .. - - - .-. - . - - ... - *--
- Nut Detected
- TABLF. 2 PAGE 3 of SURRY POWER STATION STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1980 III SOLID RADIOAeTIVE WASTE DISPOSAL ,..----- - *-*
=Isotopes
- Released:
! Units Curies Sen_tem~~ ~!kt!ili.eL-.... "'
na~omb:J (a) Total Amount of Solid Hantc Packaged I FT 3 0 3.94E+3
- 6.30E+3 1.64E+4 (b) Estimated Total Activity Curies 0 1 .451HO 1.82E+l 8.54E+O (c) Date of Shipment and frll to
{lrnwell, !11 to I c::a~nwell,
~Hrnwell to Disposition 0 ..... s-r c:: r 10-15-80 11-3-80 12-1-80 (2)
- .. 110-21-80 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 . 11-10-80 12-5-80 (2) 11-12-80 12.-8-80
' 11-13-80 12-11..:!!Qffi
!11-14-80 12.-12-80
- - 11-18-80(2) 15..:80
-- - ll-lQ-80 12-16-80 12-17-80 12-18-80 12-19-80 12-22-80*
12-30-80(2)
=~----=--=-==-=-===-=-=-=-=--==--=:*;-=- * - - ---*=-==---= - -*------ - -* -*- --* - -- -* *. - -
- *
- r TARl,E 2
.. SUllR'rPOIIEif STATION PAm*:-4-of --*- 6
- STEAM GENERATOR REPLACEMENT PROJECT
. -REPORT OP RADIOACTIVE EPFLU~ YEAR: 1981
. JANUARY
- 1 llf.BRUARY MARCH APRIL MAY '
JUNE
~~ . ~ ~--* t::::t. **-*-:1:: .*
UNt°TS I. LIQUID RELEASES Curies Isoto(!e: Released MPC ~Ci/ml *-
I-131 3 X 10-1 1. 32E-6 * * "'
I-132 8 X 10- 6 *
- I-133 1 X 10-6
- ' l~
- fr I-1Jl1 2 X 10-b * * * * *
- I-135 4 X Io-G
- 11 Ca-1Jl1 9 X 10-6 t,,OlE-4 6,00E-4 2.lO!l-4 9 .41E-4 5.21E-4 3.BSE-3 Cs-137 2 X 10-* 1.49E-] 1,60!(-3 9 .02E-l1 1.83E-3 l.28E-3 6.14E-3 Co-57 4 X 10-* 8,28E-7 l.27E-5 1.52E-7 9.09E-7 1.37E-6 2.32E-6 Co,-50 9'x 10-* l.69E-3 6.SOf.-4 2.28E-4 l.94E-3 2.27E-3 1.96E-3
!In-St, 1 X 10-* 1.BlE-4 5,00E-5 z 28E-6 9.02E-5 1.BlE-4 l.84E-4
. ii~-2/1 ] X 10 .* ,.,
- 2.00E-4 Cr-51
.. Fc-59 2 X 10-,
5 :g JO-'
2.21E-5
- ~.
l~
2.89E-5 Hb-95
- sii-121, 1 X )0-lj 2 :g 10- ~
3.07E-5
- ~-
4,DOE-6
] ,61E-6
. S.86E-6
)~
l.91E-5 9.JBE-6
- sb-lis 1 X 10- 4 ~.13E-6* 2.JOE-4 3,63E-5 l.OJg-4 1.13E-5 2.JSE-5
-zn-b5 LLJ.!l- 4
- l.25E-6 ~.5liE-b 5,39E-6
-*~r-95 * *
-- 6 x 10- b * * * * "
- Mo-99 nu-103 1 X lQ-5s . . * * "
- 8 X 10-
- k X!!-133
-xe-135 3 X 10- b 5 9lE-6 l OOE-3 * * *
- xi;=1:iJn, 3 X 10-*
- -1..1l!lE-li- * * * " *
- Ar=-ff 3 X 10-6
- l OOIHi * * * "
3 x 10- 6 * * * * --
I i\i;~:11om 3 X 10-* *
- *.** *
- 2.12E-5 --r I* 11t=r,1 3 ll 10- 5 1.0QE-6 4 lOE-7 ** .!.03E-4 R 7 ~F.-l. 4*, 87E-4 8 x 10-* **t, 1. 77E-3 -ii 2°,34E-2
. i:~-J.l,(, 1 X JO-* * *
~
1.31E-5
- If<>_,,
- rc-9<Jm 3 X m-,
HJ-5
- ** * )~
- ce-17il !I X
- volume of L19uiil to ulscl1arge Canal l.i t ....... 7.40E+S 8,00E+5 9.02E+S .8.4SE+S 7.29E+5 6.16E+S
- Not netl'cted
'l'ABT.E 2 l'AGE__ S_ _of __6 SURRY~WE!lSTATION STEAM GENF.Rl\TOR REPLACEMENT PROJEC'l' REPORT 0\1 RADIOACTIVE EFFLUENT:; YEAR: 1981 _
II. AIRBORNE RELEASES
-UNITS i~
JANUARY FEIIRUARY MARCIi APRIL MAY JUNE fu:*"isotopes Released: Curies (a} Particulates Cs-134 l.69E-5 RliF.-6 4.92E-6 Cs-137 1. lSE-4 7 .13E-6 1
l f\1'R-1' 1~R-~
5 09E-6
? 1QR~5 4
204E-5 2.43E-5 Cr-51
- Co-58
- 2.82E-4 3.31E-5 Co-60 . 5.44E-4 1.24E-4
- s*saE-s
? i;oi,_4 4.00E-4
- Rb-88 1.0SE-6 Nh-95 *
- 1 1/iF.-li M Halogens 'ii I-1:ll 2.lSE-,-6
- 1-132
- * **/;, * *
- I-lJJ I-lJ/1
.
- I-lJS * * * * * "
(c) Gases Xe-lJ3
- Xe-l.33m I
Xe-135 Kr-85m Kr-85
- *f, * * *
- Kr-87 Kr-88 Ar-ltl Xe-lJlm * *
- 11-3 5.BOE-2 ,3 ,33E-2 *
- i.2rn-2 2 20E I 1.57E+O
- 7.07E-l
!1 ----
I'
--- 1*
- --* ~-----,,-
~ -- --
-~
---....a.~,=~~- - . . . ~~--~--~.
- Nol llelectetl
TA.UJ.J~ .£.
SURRY POWER S'l'ATION l'A(:l*:..., 6 -___or_--~ ...
STEAM GENERATOR REl'i.ACEMENT PROJECT
- REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1981 JANUARY FEilRUARY MARCIi APRIL MAY JUNE Ill, SOLID RADIOACTIVE WASTE DISPOSAL Unite 0
=======================11====11-------*- -------------*-* * *-*----*--* *** *--- --- * **** * ** *------**** ** *
- __1,s.o_t_o=pe_s--::R_e-:l_ea_e_e_d_:--=-=-~,.,....=---------llt-.CU_r_i_ee--l I - - - - - ' _ , __________ _ -----1<-------11-- -*---------- - ' ------
(a) Total Amount of Solid Waste Packaged FT 3 7.48JW3 ].01E+l1 1.07E+4 4.27E+3 4.29E+3 4.10E+3
'-'--'-""------------------11-----11--.c..;----- ~------- 2. 21E+0___,,__1_.-12_E_*+-o--*ll-~5-.3~0~E-+~o--* 9
(\,) Estimated Total Activity Curies 6, 32E+O 9 * )liE-1 (c) Date of Shipment and Barnwell, Barnwell, Barnwell, Barnwell, Barnwell, Barnwell,
_____.cD_i_e.._p-'--oec...ic..t_i_o0110 _ _ _ _ _ _ _ _ _ _ _ _ _---l,-------ll--S-._c_._ _ _11_ _ s *C
- S, C, S. C. S. C, __S~.C_.___ 11 1-6-81 2-3-8] 3-2-81 4-2-81 5-5-81 *6.:.:5-81
- - - - - - - - - - - - - - - - - - - - - - l l - - - - --1.dldll___.---2=..4=131 3-3-81 4-4-8]-.--*ll--5---7--8-1--*H-6--~9::-::8=1~_-_-_-_:"
4 1-()-8) --2=5dll 3-6-81 4-9-81 5-13-81 6--::t1=~-
l-l 3-81.____ ---2=n=£)______ ~3 __
-J=0~-~8=]___11 _~4--2~1,_-_ 08~1_ _ 5-14-81 6-16-81 J-14 81 ...L:.1.0 Bl 3-11-81 4-~4-81 *s=i9-°8_1_ _ 6-2~-1--
1-15-81.____ 2-12 81 3-16-81 4-28-Hl 5-21-81 1-?0 -Rl 2-11-8]___ 3-1 7-81 5-26-81 1-?1-Rl ?-lr.-Rl 3-19-8] 5-27-81 1-?fi-ftL_ '.J-lA-111 3-20-81
11-----11------11--?--~-?~0.dJJ___ 1-,;3-::..2<...3i:-;.,.8uJ___,,__ _ _ _ _ _ ,f..- - - - - - f l - - - - - - l l
?_?0-111 1-~~-~-?......._h-~.llu:1_ _ _1r------~1-------p------11
H*----11------11------11------*ll-------11------, - - - - -
'-'=================::ll===-:c7:C:-*:l-1---,------11------1-1----- - - - - - - - - - *- *** * -
- TABLE 2A EFFLUENT RELEASE AND SOLID WASTE COMPARISON
SUMMARY
STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 1 LIQUID EFFLUENTS Total Estimated Total Actual Total 1977 Releases Releases Liquid Releases 6 6 8 Volume (gal.) 2.3 X 10 1.8 X 10 1. 4 X 10 Activity (Ci) 0.344 0.259 67.67 GASEOUS EFFLUENTS Estimated Release/Unit Actual Release During Average Six Month During SGRP Unit No. 1 SGRP 1977 Release/Unit Isotope (Ci) (Ci) (Ci)
Noble Gases Negligible 510 7400 Iodines 4.53 X 10- 3 3.27 X 10- 3 0.24 10- 3 10-3 -4 Particulates 3.12 X 2. 70 X 1.4 X 10 Tritium 8.49 4.18 120 SOLID WASTE Estimated Actual Quantities Quantities 3
Volume (ft ) 26,236 67,580 Activity (Ci) 18.9 45.0
.,... ~ .
TABLE 2B EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 1 LIQUID EFFLUENTS Total Activity Percent Released of Total Isotope (Ci) Activity Co-60 6.88 X 10-2 27 Cs-137 5.10 X 10- 2 20 Fe-55 3.65 X 10-2 14 Cs-134 3.27 X 10-2 13 Co-58 2.68 X 10-2 10
- Xe-133 Na-24 Ni-63 2.01 7.66 5,17 X
X X
10- 2 10-3 10-3 8
3 2
Mn-54 3.66 X 10-3 1 Xe-135 2,59 X 10-3 1 I-131 2.36 X 10-3 <1 All Others 1.59 X 10-3 <1 Total 2.59 X 10- 1 100
1 TABLE 2C EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 1 GASEOUS EFFLUENTS Total Activity Percent Released of Total Isotope (Ci) Activity Noble Gases Xe-133 496. 6 97 Others 13.4 3 Total 510.0 100 Iodines I-131 3.20 X 10-3 98 Others 7.16 X 10-5 2 Total 3.27 X 10-3 100 Particulates Co-60 1.65 X 10- 3 61 Co-58 4.85 X 10-4 18 Cs-137 2.90 X 10-4 11 Cs-138 1.01 X 10-4 4 Cr-51 6.07 X 10-5 2
- Others 1.16 X 10-4 4 Total 2. 70 X 10-3 100