ML18139A026
| ML18139A026 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1979 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A025 | List: |
| References | |
| PROC-791231, NUDOCS 8003050207 | |
| Download: ML18139A026 (44) | |
Text
( (.
- e STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 2 FINAL REPORT *
(PROGRESS REPORT - NO. 6)
FOR THE PERIOD FEBRUARY 3, 1979 THROUGH DECEMBER 31, 1979 DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 VIRGINIA ELECTRIC .l\.ND POWER COHPANY
/
TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
PR6-l 2.0 OCCUPATIONAL RADIATION EXPOSURES PR6-2 2.1 General PR6-2 2.2 Evaluation of Exposure Data PR6-2 2.3 Description and Format of Exposure Data PR6-3 2.4 Conclusions and Observations PR6-3 3.0 APPLICATION OF ALARA PRINCIPLES PR6-5 3 .1 General PR6-5 3.2 Initial Containment Cleanup PR6-5 3.3 Temporary Shielding PR6-6 3.4 Steam Generator Water Level PR6-8 3.5 Plasma-Arc Cutting Equipment *PR6-9 3.6 Decontamination PR6-9 3.7 Glove Boxes PR6-10 3.8 Mock-up Training PR6-ll 3.9 Miscellaneous Valve Refurbishment PR6..:.11 3.10 General Techniques and Practices PR6-12 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR6-15 4.1 General PR6-15 4.2 Airborne Releases PR6-15 4.3 Liquid Releases PR6-15 4.4 Solid Radioactive Waste PR6-15 5.0 STEAM GENERATOR STORAGE BUILDING SURVEILLANCE PR6-17
6.0 CONCLUSION
S PR6-18 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
- e*
I PR6-l SSGP
1.0 INTRODUCTION
The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 2, commenced on February 3, 1979 and was completed on December 31, 1979. 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 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. A description 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. 46 to the operating license for Surry, Unit No. 2 and, as such, completes and fully satisfies the requirements set forth in those conditions.
PR6-2.
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 (manrern) 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.
I, 1 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 wany tasks performed.
( (
e e PR6-3 SSGP.
2.3 Description and Format 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 performed 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 rec~ived by personnel .per-forming 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 l_ J upon the major activities being performed at the time they we re incurred.
(b) Due to an unrelated extension of the Unit No. 2 outage, several SGRP tasks associated with refueling and startup acti-vities had not yet been completed as of the project end date of December 31, 1979. For these remaining tasks, the "actual" expenditures reported have been assigned the original esti-mated values, and are appropriately noted as such in Table 1.
(c) 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 unassign~d 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. 2 was approximately 4%, or 74 manrem,
e- *...
- PR6-4 SSGP above the exposure estimate of 2,067 manrern. While this smail percentage is not considered to represent a significant de-viation from the total exposure estimate, several individual tasks did vary considerably with respect to estimated vs.
actual exposures. In most cases, the major factors to which these variations can be attributed are: changes in original work scope, methods or procedures, actual radiation dose rates higher or lower than estimated, unanticipated problems with equipment or procedures, or personnel (contractor) changes.
(b) During the repai~ effort, no worker assigned to the SGRP re-ceived radiation exposure in excess of the federal standards specified in 10CFR20.
( c) The actual labor expenditures (manhours) reported in Table 1 I, J exceed, in most cases, the estimates made during the project planning phase. This is largely attributed to the fact that peripheral and 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.
- * ** PR6-5 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 pennits, the following evalua-tions include a quantitative assessment of the manrem savings which can be attributed to the technique used. Additional information on
~hese techniques and how they relate to the overall steam generator replacement act ivfties can be found in the SGRF Report.
3.2 Initial Containment Cleanup I, J 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. 23 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 "Friske rs" and portal monitors, to detect radiation on body surfaces, identi-fied no instances of significant internal or external personnel contamination during the repair program.
- ****** PR6-6 SSGP The worker's ability to perform tasks more efficiently, and thus complete them more quickly, undoubted~y re~ulted in a reduction of the time spent in radiation areas. Considering the large number of workers involved ( in excess of 1,000), even a 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
,_ J 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 mini.iuum 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 obt~ined prior to and after shielding installation permits the cal-culation of average dose rate reduction factors for appropriate
PR6-7
. SSGP tasks, and thereby an assessment of manrem savings. Three tasks 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 214 manrem. Con-tact exposure rate measurements obtained during surveys has shown that an average dose rate reduction factor of 7 was achieved by shielding Gf this pipe. Using this factor and the actual exposure value for the task, a postulated expenditure of about 1,500 manrem would have been required to complete the task without the benefit of shielding. An assumed savings of 1,286 manrem can thus be credited.
(b) The removal of miscellaneous piping located in the steam gene-rator cubicles accounted for the expenditure of approximately 59 manrem. Shielding applied to this pipe provided an average dose rate reduction factor of 5. Thus, without shielding 295 manrem would have been required to complete the task. A savings of 236 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 the removed pipe sections. In Table 1, the installation of reactor cool-ant piping is reported to have required a total expenditure of 329 manrem. The activities performed inside the generator cubicles are estimated to account for approximately 300 rnanrem of this total. Survey data indicates that shielding performed for these activities was effective in reducing dose rates by a factor of 5, and thus resulted in a savings of 1,200 manrem.
Totaling the exposure savings calculated for the above three tasks results in an overall savings of about 2,700 manrem attributable to the use of temporary shielding. The exposure "cost" incurred during inst&llation of shielding is listed in Table 1 as approximately 143
PR6-:-8.
SSGP manrem. A comparison of these "benefits" and "costs" provides a clear indication of the value of this technique in maintaining occu-pational exposures AI.ARA.
3.4 Stea3 Generator ~ater Level In the early stages of the SGRP, the water in the secondary system was ~aintained 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 70 manrem.
The observed dose reduction factor of 10 thus translates into a postulated exposure savings of 630 manrem. Since practically no exposure "costs" were required to utilize this technique, its contribution to tr.e ALARA program is obvious.
e** ...- PR6-~
SSGP 3.5 Plas~a-Arc Cutting Equipment In order to remove the steam generator lower shells from the con-tainnent, sections of the reactor coolant piping were cut and removed. A plasma-:-arc cut ting torch was chosen as the means for perfon:::ing these cuts. Plasma-arc has high cutting speed and pro-duces good cut quality for pipe reuse. The high cutting rate was a priEary factor in this choice since faster cutting means reduced exposure times. During the evaluation of this task, alternate methods such as mechanical cutting and other flame cutting tech-niques ~ere considered. These alternatives were estimated* to require l to 4 ho~rs per cut, as cocpared to 15 to 20 minutes for plasr::a-arc. In actual use, most of the reactor coolant pipe cuts were performed in approximately 20 minutes with the plasma-arc torch.
One cut required about 30 minutes d1.1e to mechanical interference.
Equip,ent set-up times were estimated to be about the same for all methods considered, since all would require special track mounting to ~aintain the close tolerances necessary for reuse of the reactor coolant pipe.
The exFosure 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 pipe 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 tr.e AI.ARA committment.
3.6 Decont~~ination Sections of reactor coolant pipe cut from the primary system during the re=oval phase were decontaminated prior to refurbishment and reuse. Tne electropolishing process used for pipe decontamination is des~rioed on page 9.C.3-1 of the SGRP Report. Prior to decon-
- -tau,inc. tion, radiation surveys of the removed pipe sect ions revealed average contact readings of 5,000 to 10,000 mR/hr on the inside pipe surfaces. Average contact readings after decontamination were nooi~a:ly 1 to 5 mR/hr. Surface irregularities prevented one pipe
A*. . ,.
~ - - *....
PR6-10 SSGP section from decontamination below 30 mR/hr on contact, however, levels at the pipe ends, where refurbishment and welding were per-formed, were measured at 3 to 5 mR/hr. Based on these measurements, an average dose rate reduction factor of 1,000 can be attributed to the use of the electropolishing technique.
An assessment of the exposure savings which have been realized from this technique is difficult due to the fact that refurbishment work performed on the decontaminated pipe sections was not reported separately from the pipe stub refurbishment performed in the steam generator cubicles. Also, the exposure received during subsequent fit-up_ and welding of this pipe resulted largely from other sources within the generator cubicles, and not from the pipe sections them-selves. It has been estimated, however, that approximately 10 to 20 manrem were expended during the refurbishment (i.e., machining and weld-prep) of this pipe. Without decontamination, .this task alone could thus have required 10,000 to 20,000 manrem. The total decon-tamination "cost", in terms of radiation exposure, was approximately 41 manrem. While the calculated exposure savings above are merely projections, they serve to illustrate the value of this important ALARA technique.
3.7 Glove Boxes The use of tents and glove boxes for all cutting and grinding acti-vities involving contaminated piping was required during the Unit No. 2 repair program in an attempt to maintain low airborne con-tamination levels within the containment. Ideally, the glove box would al low personnel performing pipe cuts or other related tasks to work without the need for personal respiratory protection, thus increasing efficiency and reducing exposure times. Controlling the spread of contamination through use of this equipment would also facilitate cleanup operations. However, close monitoring of seve-ral cutting operations found that more exposure was expended in installing and removing the glove boxes than in performing the actual pipe cut. Typical exposures for inst al lat ion and removal combined were, in some instances, 50 times that received by the
- PR6-ll SSGP worker performing the cut. Also, cleaning of the pipe surfaces in the cut area greatly reduced the potential. for generating signifi-cant airborne contamination. Actual sampling for airborne radio-activity during cutting operations confirmed that in most cases no significant hazard was created. Based on these observations, it is now evident that the use of glove boxes for pipe cutting and similar tasks should be evaluated on a case by case basis to deter-.
mine if such is prudent from an overall ALARA consideration.
3.8 Mock-up Training The installation of reactor coolant piping represents the most significant task performed during the repair effort with regard to occupational exposure. While the shielding and decontamination techniques described earlier were effective in reducing the radia-tion exposure rates associated with this task, the use of mock-ups to train the workers involved can be credited with providing reduc-tions in exposure times. Welders, pipe-fitters, riggers and laborers.
all received extensive training in the activities to be performed by "dry runs" in ful 1 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 ALAR.A program.
3.9 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 were much
e- **... PR6-12 SSGP lower. General area exposure rates in the pipe refurbishment build-ing were approximately O. 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 was minimized.
Since the miscellaneous piping systems contained radioactive con-tamination, the removed valves represented a source of radiation exposure during refurbishment and reinstallation. Some of these valves 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 required less ex-posure to personnel.
The total exposure expended during.the repair effort for "Installa-tion of Blowdown and Miscellaneous Piping" was approximately 84 manrem. Of this total, installation of miscellaneous piping (and valves) represented about 25 manrem. Considering the exposure re-duct ions *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 exposure savings of about 225 manrem.
3.10 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 were implemented prior to and during the repair effort to assure adequate control of occupational radiation ex-posure and to maintain this exposure Al.ARA. 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 radiatio_n
PR6...,.13 SSGP 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-denced 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 steam generator replacement activities. Training for specific tasks, using rnock-UJ:)S, 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) Special tools and equipment, designed to minimize personnel exposure times by increasing worker efficiency and providing remote handling capability were utilized where practicable.
(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 will be of significant benefit in training or retraining of personnel for the Unit No. 1 Steam Generator Replacement Project.
PR6....,14 SSGP (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.
(h) Piping, valves and other components which req~ired refurbish-ment prior to reuse were removed from the containment to allow this work to be performed in an area where exposure rates were lower. A special refurbishment building was constructed for this purpose.
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.
PR6-15 SSGP 4.0 RADIOACTIVE EFFLUENTS Ai.~D SOLID WASTE 4.1 General Radioactive liquid and gaseous effluents, and radioactively con-taminated solid wastes generated during the SGRP for Unit No. 2 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 the 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 releases 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 distribution of the major isotopes released in liquid effluents is presented in Table 2B. It should be noted that the concurrent outage for Surry Unit No. 1 during the period March through September may have contributed to the quantities of radio-active liquids released to the discharge canal. This contribution could not be assessed quantitatively, however, since a shared laundry facility is used for both units.
4.4 Solid Radioactive Waste The solid radioactive waste generated during the repair effort consisted of: (i) contaminated insulation, structural materials,
PR6-:16 SSGP and components not intended for reuse, (ii) solidified decomtami-nation solutions, and (iii) contaminated paper waste, disposable protective clothing and contamination control materials.
PR6-17 SSGP 5.0 STEAM GENERATOR STORAGE BUILDING SURVEILLANCE Since the old steam generator lower assemblies removed from Unit No. 2 were placed in the onsite, engineered storage building, a surveillance program has been in progress to assess the performance of this facility. Radiation surveys performed on the outside of this building have shown average contact exposure rates of between
- 0. 01 and O. 09 IIL.~/hr. Approxima_tely 1,100 gallons of water have been removed from the building sump. The presence of this water has been attributed to rainwater intrusion; as the building has only been temporarily sealed pending storage of the Unit No. 1 steam generators. Analyses of this water have detected no radio-active contamination. Samples of the installed HEPA filters have been analyzed and, as yet, no radioactive particulates appear to be present. This surveillance program will continue at its current level for one year, at which time the data obtained will be evalu-ated and a permanent program established.
- -*** PR6"""718 SSGP 6.0 CON CL US IONS The following general conclusions are based upon the information contained within this report.
(a) Although some variations can be seen when comparing the esti-nated vs. actual exposure expenditures for individual tasks, the total exposure (manrem) expended during the repair effort for Unit No. 2 is not significantly different from the origi-nal estimate established prior to commencement of work. This result, and the techniques described in Section 3 which *have played an important part in achieving it, confirm that the ALARA concept has been effectively implemented and applied to the steam generator replacewent activities. Nevertheless, the experience gained during this project provides a valuable tool for effecting further improvements and refinements to future replacement activities.
b) Radioactive liquid effluents exceeded the total release estimate for activity presented on page 9 .A. 5-5 of the SGRP report by approximately 51%. The total volume released, however, is only 30% higher than the estimated total. This indicates that liquid effluent concentrations were somewhat higher than originally anticipated. It has also been noted that some contributions to the liquid releases reported have occurred due to the concurrent outage for Unit No. 1. Never-theless, the total activity released during the repair program represents less than 1% of that normally expected during station operation.
(c) Radioactive gaseous effluents released during the repair pro-gram were comparable to or less than the estimates established in the SGRP Report on page 9.A.8-7. The reported nob le gas releases occurred as a normal result of the defueling opera-tion and, as expected, were not evident during the remainder of the project. Radioiodine releases were much lower than originally estimated and disappeared altogether very shortly
PR6-19 SSGP after shutdown due to their short half-1 ives. Radioactive particulate releases were lower than. but comparable to the estimated quantities.
(d) Solid radioactive waste generation for the repair program exceeded the volume and activity estimates set forth on page 9.A.9-2 of the SGRP Report. This has been largely attributed.
to the increased numbers of personnel assigned to the SGRP, and the expected subsequent generation of higher volumes of contaminated paper waste, disposable protective clothing and contamination control materials. Additionally, the need for improved management and control of non-compressible materials (i.e., scaffolding, wood, tools, etc) introduced into con-taminated areas has been recognized.
(e) Surveillance data obtained thus far indicates the following with respect to onsite storage of the old steam generator lower assemblies.
(i) Radiation levels measured at the outside wall of the storage building are less than O. 1 mR/hr on contact.
This is less than the estimated level presented on page 9 .A.16-3 of the SGRP Report and, thus, the resulting radiation level at the site boundary (or nearest unre-stricted area) will be less than 0.0001 mR/hr, as antici-pated.
(ii) Rainwater intrusion has been attributed as the source of the water removed from the building sump. Analyses have detected no radioactive contamination in this water, and this intrusion should cease once the Unit No. 1 genera-tors are placed inside and the building may be permanently sealed.
( iii) Samples of the building EEPA filters have contained no detectable radioactive particulates; an indication that clean and stable airborne conditions exist within the building ..
Page l of 15 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
STEAM GENlmATOR REPLACEMENT ACTIVITrns SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED
- EXPOSURE EXPENDED I
II
~!ASE DESCRIPTION Shutdown and Preparatory Activities Removal Activities (MANHOURS) 39,021 57,422 (MANHOURS) 142,76!1 159,751 (MAN-REM) 596. 27 559.6 (MAN-REM) 344.262 602.335 III Installation Activities 74,195 389,153 l1l18.23 748.324 IV Post Installation and 62,650 90,502 427.54 179.230 Startup Activities V Steam Generator Storage 300 3,659 35.0 5.054 Activities SUBTOTAL Additional Tasks and Unassigned Personnel 233,588 785,829 85,814 2,066.64 1,879.205 261.427 Categories PROJECT TOTALS 233,588 871,643 2,066.64 2,ll,0.632
Page 2 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LAROR ESTIMATED ACTUAL EXPOSURE TASK DESCRIPTION LABOR (MAN HOURS)
EXPENDED (MAN HOURS)
EXPOSURE (MAN-REM)
EXPENDED (MAN-REM) e,,
Erect Equipment Hatch 264 1,073 0.4 0.459 Temporary Exposure Prepare and Load Test 210 2,757 1.05 2.883 Polar Crane Open Equipment Hatch* 156 ------ 0.23 -------
De fueling and Fuel Storage 585 3,437 11. 7 22.124 Inst<1ll Reactor: Vessel Cavity Cover Installation of Jib Cranes 130 1,838 2,385 13 ,L105
- 1. 3 9.19
- 1. 972 14.822 .,
Disassemble Manipulator Crane 58 1,501 1. 7L1 2.416 Install Steam Generator 572 7,527 2.86 13.095 Transport System Removal of Biological 1,296 3,959 19.44 3.392 Shield Wall Disassemble Shroud Cooling 150 918 3.0 1.520
- System
Page J of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SIIUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATTON - UNIT NO. 2 ESTIMATED ACTUAL LABOR l~STIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION Cutting of Crane Wall at (MANHOURS) 432 (MANHOURS) 1,379 (MAN-REM) 2 .16 (MAN-REM) e
!latch Opening Installation of Temporary 50 0.05 1,.210 Ventilation System Temporary Scaffolding 7,500 14,559 75 74.363 Temporary Lighting 5,200 6,609 26.25 0.563 and Power Cleanup and Decon 9,000 17,216 135 22.601 Polar Crane Operator 1,500 1,368 4.5 2.319 Shielding 3,600 21,930 270 143.493 ll.P., Q.A. 31,286 32.4 PHASE I SUBTOTAL 39,021 142,764 596. 27
Page 4 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SIIUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
ADDITIONAL TASKS Installation of Service 2,491 0.670 Air System Work Platform 5,272 0.181 Modification Removal of Reactor 1,357 4.621 Coolant Pump Motors Protection of Containment 1,094 4.054 Components UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 5.657 II Craft Support and 10 .000 Security Escorts II Project Supervision 17.227 and Administration II Visitors and 1.235 Inspectors
Page 5 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
SUllTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.)
10,2]/, ------- !13. 6L15 PHASE I PROJECT TOTAL 39,021 152,978 596. 27 387.907
Page 6 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVTT.rns SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION
!{emovu L of l n s u la ti.on (MANHOURS) 720 (Mi\NHOURS) 2,026 (MAN-REM) 28.8 (MAN-REM) 13.791 e-,
(lower shell, RC Piping)
Removal of Insulation (upper shell, 864 80 12.96 1.364 mainsteam and feedwater piping)
Removal of Miscellaneous 72 5,424 1.8 59.337 Piping Set Up Steam Generator l, 152 224 28.8 0.229 Girth Cut Equipment Cut and Remove Steam 330 5,079 8.25 11.221 Generator Upper Shell Cutting of Reactor Coolant Piping Cutting of Mainsteam and 2,982 1,428 20,235 2,838 149.1 7.14 214.058 1.132 Feedwater Piping Disassembly of Steam 792 10,791 15. 8L1 49.021 Generator Supports Removal of Moisture 396 6,050 1.98 6. 727 Separation Equipment Refurbish Steam Generator 9,246 21,756 46.23 19.819
. Upper Shell
Page 7 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURI~
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Removal of Steam Generator Level 135 2,311 I~ .OS 7.671 Instruments and Blowdown Piping Removal of Steam Generator 1,575 3,859 31.5 29.875 Lower Shell Temporary Scaffolding 7,500 11,969 75.0 46.464 Temporary Lighting 5,250 6,071 26.25 5.910 and Power Cleanup and Decon 17,000 26,731 85.0 83. 718 Polar Crane Operator 1,500 1,308 4.5 1.038 H.P., Q.A. 6,480 32,999 32.4 50. 960 PHASE II SUBTOTAL 159,751 559.6 602.335 ADDITIONAf, TASKS Material Handling, Equipment 30,991 53.897 Maintenance, and Miscellaneous
- Construction Activities
Page 8 of 15 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
UNASSIGNED PERSONNEL CATEGORIES J*'.11g I n(!l! 1:1.ng Suppo1: t Not Reported Li. B58 II Cruft Support and l. 281 Security Escorts II Project Supervision 37.579 and Administration II VisJtors and 0.300 Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.)
PHASE II PROJECT TOTAL 57,422 30,991 190,742 559.6 97.915 700.250
Page 9 of 15 TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LAl30R EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION Steam Generator Lower Shell Installation (MANIIOURS) 1,926 (MANHOURS) 12,696 (MAN-REM) 9.63 (MAN-REM) 18.300 ---
Installation of Reactor 6,768 90,695 67.68 329.181 Coolant Piping Steam Generator 5,400 41,853 27.0 17.578 Girth Weld Installation of Main 3,735 12,9116 18.68 17.299 Steam Piping Installation of Feedwa ter 2,700 7,727 13.5 3.985 Piping Installation of Blowdown and Miscellaneous Piping Install Steam Generator 1,782 2,592 21,638 14,718 17.82
- 12. 96 83.942 18.496 Level Instruments Installation of 11,562 11, 562** 57.81 57.810**
Insulation Temporary Scaffolding 7,500 15,282 75.0 39.298 Temporary Lighting 5,250 13 ,!1 91~ 26.25 8.795
- and Power
Page 10 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Cleanup and Decon 17,000 58,820 85.0 96. 704 Polar Crane Operator 1,500 3,205 4.5 1.252 H.P., Q.A. 6,480 32.4 5.5.684 PHASE III SUBTOTAL 74,195 389,153 448.23 748.324 ADDITIONAL TASKS Material Handling, Equipment 38,739 18.999 Maintenance, and Miscellaneous Construction Activities UNASST.CNED PERSONNEL CATEGORIES Engineering Support Not Reported 5.783 II Croft Support and 1.390 Security II Project Supervision 79.628 and Administration
PagL! I l of 15 TAIILE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III - INSTALLATION ACTIVITIES SURRY POWlm STATTON - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION Visitors and (MANHOURS)
(Mi\Nl!OURS)
Not Reported (MAN-REM)
(MAN-REM) 0.329 e--
Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.)
38,739 ------- 106.129 PHASE III PROJECT TOTAL 74,195 427,892 Li48. 23 854.453
.... , ..... ' , **..*.. , ..... , .* ,., .*.,,., ,,,,,,,.,;.,, *.*. ,,,.,,.*1t***t***,,*,1 ,,,,, ...* , .* ,,,1\>' ,:-.*-.. ..;..
Page 12 of 15 TAJILI~ l PERSONNEL RAIHATION EXPOSURE
SUMMARY
PHASE IV - INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)
Install Biological 3,240 1,499 16.2 0.997 Shield Wall Repair Crane Wall 4 73 336 2.37 0 .1,00 Opening Install Steam Generator 9,000 37,251 90.0 67.739 Recirculation and Trans'fei: System Remove Reactoi: Cavity 130 289 0.65 0.351 Cover Inslnll Renctor Cavity 2'10 8/17 1. 2 0:731 Coaming Reassemble Manipulator Crane Remove Steam Generator Transport System 1,176 425 1,016 143 23.25 2.12 1.176 0 .187 Reassemble Shroud 576 3,451 11. 52 11.520**
Cooling System Uydrostatic Tests 75 2,324 0.38 3.358 Refueling 585 585** 11. 7 11.700**
Page 13 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PIIASE IV - INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR . ESTIMATED ACTUAL EXPOSURE LABOR EXPENDED EXPOSURE EXPENDED TASK DE SCRIPT [ON Temporary Scaffolding (MANHOURS) 7,500 (MANIIOURS) 2,726 (MAN-REM) 75.0 (MAN-REM) 7 .136 e
Temporary Lighting 5,250 2,269 26.25 1.019 and Power Cleanup and !)econ 17,000 10,711 85.0 20.928 Polar Crane Operator 1,500 1,009 4.5 0.367 Painting 9,000 9,000** 45.0 45.000**
II. p. ' Q.A.
PHASE IV SUBTOTAL 6,L180 62,650 17,046 90,502 32 .L1 427.54 6.621 179.230 ADDITIONAL TASKS Material Handling, Equipment ------ 5,870 ------- 2.305 Maintenance, and Miscellaneous Construction Activities
TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV - INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL l~Xl'OSUIU:
LAnOR EXl'ENIJED EXPOSURE EXPENDED TASK DESCRIPTION UNASSIGNED PERSONNEL CATEGORIES (MANl!OURS) (MANl!OURS) (MAN-REM) (MAN-REM) e--.
Engineering Support Not Reported 0.805 II Craft Support and 0.794 Security II P~oject Supervision 9.812 and Administration II Visitors and 0.022 Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) 5,870 13.738 e-PHASE IV PROJECT TOTAL 62,650 9~,372 427.54 192. 968
. *::.:::*:* :::*::::::::::::**: ~-
Page 15 of 15 TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE V - STEAM GENERATOR STORAGE ACTIVITIL~S SURRY POWER STATION - UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED ACTUAL EXPOSURE Steam TASK DESCRIPTION Gene nrtor Act.Lv 1.t.lei; Storage LABOR (MANHOURS) 300 EXPENDED (MANHOURS) 3,659 EXPOSURE (MAN-REM) 35.0 EXPENDED (MAN-REM) 5.054 --
TABLE NOTATION
- 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.
- These expenditures were estimated since the tasks involved were not yet completed as of the project end date of December 31, 1979.
1:~1_1_1." .1:. PAGE 1 OF 4 Sllllll\' l'O\Jlrn S'l'i\TJOII sn;/111 c:1ctrn1tA'lllll IU-:l'J.AC.:EIIEll't' f'll0.IEC1' llEPOllT OF JlADJOi\C'fl VE EFFLUENTS YEAR: _ _....;l'-'9c...:7....:c9_ _
Not ll!!tl!t:tcd Includes nidloactivc liquid uuste generated during Unit No. l outngl!.
TABI.E 2 PAGE 2 OF 4 Sl!RHY POI/EH STATIOH S'l'EAII (:r-:m:UArnn IIEl'I.AC:EllEtlT PRO.IRCT REl'OllT 01' nAlllOACTI V~- lffFLIIEllTS YEAR: _ _ _1_9_7-'-9_ _
~I
______ (h) __Ila logl.~11!.1 * *------ * **---------
1-1 "If
______ , -1:12 __ --- * --
I< A A ---r A
_____ .l::.1-1)________ .. ----.* - - : - - - - - - : - - - - - - - : - - - ~ - :-:=----_-_-__
_____1 = . u 1 1 _ ------*u----
- _ _ _ _ ---~---* .-,.-----
____ J..=J..1'.l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - , 1 - - - - - - * - - - - , - - - - * - - - - - - - - - - ~ -_ _ _ _
- ---rcn.a,'"" -
~-------~~=--11-J~----------------- - - - - :* --:---- - : : -_-_-_ :~~:::::~::_-_-_,------
, _ _ _ _ ,,_!!_::.*. ../.!U----------------H----fi------ 1---,1<~--- 1
- *- i, ----- ** ~ - - - - - ! - - - - -
______ )(c,-] l'> * - - - - - - - - - - - - - - - - - - - - -*-- ---"----!1---,------1----- * -,.,----- -.--*---
,---~t;!:::.!!_~1_11__________________ - - - - --**___ --~---* L L ** --:.--*-*!------
K1*-ll5
____ Kr::!} --- - ,.---*
ff
.--- --.----1---,.-----,1~
w "
--1-------1
_____ Kr..::!!0,_____________________ ,__::::=_- ___* ___ =._-=._-_-*=:_-_-_-_. _ "' ;, -- -1,------ u------i Ar-t, I * * * '~ - 1-----*
A--------------------- - - - - - ------
l.ll.~'i!ll.llLRAUlOA<:1'.L\llt.H/iSU:.JllSl~lSAL~---11-----<-------*------
(a) Totnl Am,111nt Sol I.,! IJa,ac rncka1;cd l*i' 3 0.701,t-J J..66E+) 2.8)Ji+) 1,251:+J 0
_ 1J.i(c) 1'::;1.l11r1L;,,( Tol11l t\ct1vlty Date of 5hlp111e111. nnd Curleu
- "-T,~1-:-1U-llnrmrnlI, 1.u,1,:10
- ll11rnwel.l, _ llarnwell, l * .IOKIO _ J-:71l1*:=-2 llnr:1111<,l _____
I, 1r*.~----~-~-~--:=----~-! -A-.¥----=-----.-~-=---~-=-=~.I 11------ll_l_SE!!_~tlon S.C, S.C, S. C, S. C.
- ,-***="***==-*-*-*-~*"=--**==*,~~-,=*~-*--***-*-=* --~-' rr.::2::a1iJ'~~--~ **,r~r1.:,Ir=*--*-~~1t:w::1!r=-A~1y:1:::.7i)-~ 0
- -~-~,u*a~a. 4 O-l0-79 9-25-79 10-9-79 8-17-79 10-10-79 8-'21-79 ())
8-211- 79 (!,)
TA!ll.E 2 P/IGg _3_ Of t,
- SIJHJlY rmmn ST/ITCOII STEAII (:1m1m/lTO!l lll\l'I./ICEli1rnr l'llO.rnCT llEl'OllT OF ll/l!JlO/ICTlVI! EFF1,1mrn-s YEAR :. _ _---'l9'-'7...a9_ _
- ----""~"" ....... --- .,_...,..._,,_________ .
*-* .* n~1rnul.\u:L~- _.*u~ur.1t._ .... __ /\PHU, .. ,__
.MJV\Y ~ ...***--*
~
--~.1:!'!.1~.v~*- _ Jm.v **- ~.
1.. 1.rq111u llEI.E/1:.ES UIHTS
--.r
__ Vo.lure of Llquid to lliochai:ge Canal Ll.ters -S:-971~rr-- -r.-,ml~ ~:-6lmrs-- 1.IIE*lli l~llb 9.9JE+5
- - - - - - - - - - - - * - ------11-------1--':..:..:~c:......::_ - - - -
- Air Id,.
- Not Octcctcil
- -* l11cludcs rndloactlvc ll<Juld uasll!
generated <luring Unit Ho. l outage.
PAGE ...!!._ OF 1*
TABLE 2 Slll\HY l'Otmn STATION
- TEAii c
- 1rn1rnATOI\ lllil'l,ACl:tll:trr PHO.IECT ltEL'OllT OF llAl!lOAGTI VE EFl'l,lJEIITS . YEAR '---'-I9'-7'-C9'----
l l. AIRUORNE REI.EASES
___ -(l0llnlt1t,en,1_
______1-111 ______________________ ~
l.-1]2
-"T.o,rn-6--
-.-----* - . - - - - - ._*____ --~-----
______ l::J.JJ, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ----H---*----1 * * -.--- I< ...,.---
. ____..J..::l)/1 ___________________ , ___ ,. _ _*____ , ___ .___ *
- _ _ ---1.=J_J'.j __________________ ----*---*--- ---*--- **-*:~_-_-_-_-_-_-,;_*--*---=--=--=--=-*:.-::.=*======= "
---(c) Ga,ic,i
____ Xc-l)J ----* -~p;~. J.001110 . *
--r---- -.~----*-~----*-~--- - *
,1
--- * - -------11-----
_____X!,.:: l.J),n _______________ l----11-~~~,,.--
I ,c 1. 91,E+O *
- X
,,_ -~ c>_- - - - - - * - - - - - - - - -
- - - - - K r-ll51.11.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1---~---1--~----ll--,,-------l--,~---*J---.---- *
- - ; , ; ; - - - ----,,.--- --~.----!*-,.----- ---,.---
.______ K,*-ll5 - - - - - - * - - - - - - - - - - - - , - - - - - ~ - - - - - - , . - - - - - . - - - - - * - , ~ - - - *
- ---- Kr-ll7_ -*- - - - * - - -- - - - ---;,;;--- * * . ..---- "*
~~J,ly------*--------------- ---- ---;,--*---.,.--- --.---- " "
- ---------*--------------------- * - - - - - - - - ------- *------ * - - - - - ------ -------1 lU._SCll,lll IVI.IIUlAC:Il'llUlll!iTILlll!il'.llSAI. ____ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - -
(11) Tolnl Amount Solid \.lnste l'ach:q:i:,I n-' J.6'.iEI*] l.lJl\1./o 6.921::IJ Ci.GOm*J 'l.)01113 7. 711EI*)
- (1,J 1,,;L1111n1i,(J TotalActlvlty .. - - Curlen -9.97.E-l-- ).T6K10-- -Z.7GEl,r-- --.,,:*~Jf*JIO- LOJE+J 6,90E-IO--
---(c)--O,;l;;-nr si,Lpment 1111<1 11;;:;;-;;;;ll, llarnwcll, narnel'l.ll, llarnwoll, lla~wcd_l_,_ -namwerr:-
. ______ Dl!jr!>Hltlnn _ _ _ _S,C _!i ... C.___ _1;.c.___ S.C. _ _ _ . _ ; ~ - -~.:.~---
- ...... -....... ,. ...... --. ~ .. ~ ~ - r o , , * - . --~---~ - - - ... ---'"*2 19-.~-J-6~ 79~--J-1 /-7!1= 4-C,- 79 i4 l *=5--5--71.,"' , ~--r.- )':79"-* -~7:.. Fn"~~*-*
2-22-79 J-7-79 J-19-79 4-')-7') 5-ll-7'J ,,-7-79(3) 7-10-79
'Nol I,:, l e<<:l:ed 2-27-7'1 J-U-7'1 J-211-7') ,]-12-79 (2) 5-lfr-79 6-11*-"/9 7-l)-79 (t*) .June date of ahlpmt!Uln continued 2-20-79 J-Ll-79 )-28-19 4-14-79 5-19-79 Ci-lJ-79 7-16-79 6-25-79,6-26-79,6-27-19 )-1)-79 )-29-79 4-1:/-79 5,;2.1-79(2) 6-llo-79 7-10-79(2)
J-15-79 J-2'J-7'.l '1-22-7'1 5-25-7'.l (2) 6-15-79()) 7-20-79 5-29-7') 6-22-79 7-2]-79 5--J0-79 (2) (,- 7 l,-1'1 7-211-79
(+)
TABLE 2A EFFLUENT RELEASE AND SOLID WASTE COMPARISON
SUMMARY
STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 LIQUID EFFLUENTS Total Estimated Total Actual Total 1977 Releases Releases Liquid Releases Volume (gal.) 2.3 X 106 3.0 X 106 1.4 X 108 Activity (Ci) 0.344 0.519 67.67 GASEOUS EFFLUENTS Estimated Release/Unit Actual Release During Average Six ~1onth During SGRP Unit No. 2 SGRP 1977 Release/Unit Isotope (Ci) (Ci) (Ci)
Noble Gases Negligible 101.3 7400 Iodines 4.53 x 10-3 6.88 X 10-6 0.24 Particulates 3.12 x 10-3 1. 32 X 10-3 1.4 X 10-4 SOLID WASTE Estimated Actual Quantities Quantities Volume (ft3) 26,236 57,790 Activity (Ci) 18.9 63.6
TABLE 2B EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 LIQUID EFFLUENTS Total Activity Percent Released of Total Isotope (Ci) Activity Fe-55 1.41 X 10-l 27 Co-60 1.04 X 10-1 20 Co-58 1.01 X 10-l 19 Ni-63 6.79 X 10-2 13 Cs-137 4.93 X 10-2 10
-i Cr-51 2.46 X 10-2 5 I
~ I Cs-134 2.24 X 10-2 4 Mn-54 5.08 X 10-3 1 All Others 3.26 X 10-3 1 Total 5.19 X 10-l 100
TABLE 2C EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION - UNIT NO. 2 GASEOUS EFFLUENTS Total Activity Percent Released of Total Isotope (Ci) Activity