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
1.0 INTRODUCTION
2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General 2.2 Evaluation of Exposure Data **** *... 2.3 Description and Format of Exposure Data 2.4 Conclusions and Observations 3.0 APPLICATION OF ALARA PRINCIPLES 3 .1 General 3.2 Initial Containment Cleanup 3.3 Temporary Shielding 3.4 Steam Generator Water Level 3.5 Plasma-Arc Cutting Equipment 3.6 Decontamination 3.7 Glove Boxes 3.8 Mock-up Training 3.9 Miscellaneous Valve Refurbishment 3.10 General Techniques and Practices 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General 4.2 Airborne Releases 4.3 Liquid Releases 4.4 Solid Radioactive Waste 5.0 STEAM GENERATOR STORAGE BUILDING SURVEILLANCE
6.0 CONCLUSION
S i PAGE NO. PR6-l PR6-2 PR6-2 PR6-2 PR6-3 PR6-3 PR6-5 PR6-5 PR6-5 PR6-6 PR6-8 *PR6-9 PR6-9 PR6-10 PR6-ll PR6..:.11 PR6-12 PR6-15 PR6-15 PR6-15 PR6-15 PR6-15 PR6-17 PR6-18
- -*** 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
1.0 INTRODUCTION
I e* PR6-l SSGP 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 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 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.
- 2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General '. *** .. .. PR6-2. SSGP Occupational exposure to radiation is considered to be the major radiological effect of the SGRP. As such, this aspect of the 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. 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 I, 1 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 pended on the wany tasks performed.
( e 2.3 Description and Format of Exposure Data ( e PR6-3 SSGP. Table 1 presents a summary of the occupational radiation exposure expended during the repair effort, the exposure related labor 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 forming functions not directly attributable to any specific, pre-defined task have been listed separately.
Expenditures reported for these "Additional Tasks" and "Unassigned 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 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 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 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 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 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 ities.
- 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General * ** PR6-5 SSGP This section summarizes the specific techniques and practices which were employed during the repair effort in order to maintain 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 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, 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 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, fied no instances of significant internal or external personnel contamination during the repair program.
,_ J *** *** *****
- 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 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 vided a basis for evaluating the effectiveness of temporary ing in achieving net reductions in personnel exposure.
Survey data obt~ined prior to and after shielding installation permits the 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. 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 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 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 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 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 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 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 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 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 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 tion exposure rates associated with this task, the use of mock-ups to train the workers involved can be credited with providing 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 ment building outside the containment where exposure rates were much e-* *... PR6-12 SSGP lower. General area exposure rates in the pipe refurbishment 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 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 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. of each is given below. A brief description (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 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 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 buting to the overall ALARA program for the steam generator ment project.
4.0 ...
- RADIOACTIVE EFFLUENTS Ai.~D SOLID WASTE ..... . .... PR6-15 SSGP 4.1 General Radioactive liquid and gaseous effluents, and radioactively taminated solid wastes generated during the SGRP for Unit No. 2 are summarized in Table 2. given below. A description of each category is 4.2 Airborne Releases 4.3 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. 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 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 nation solutions, and (iii) contaminated paper waste, disposable protective clothing and contamination control materials.
5.0 ** ., .. STEAM GENERATOR STORAGE BUILDING SURVEILLANCE PR6-17 SSGP 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 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 ated and a permanent program established.
6.0 ** ** CON CL US IONS -*** PR6"""718 SSGP The following general conclusions are based upon the information contained within this report. (a) Although some variations can be seen when comparing the 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 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. 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 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 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
- ., ... after shutdown due to their short half-1 ives. PR6-19 SSGP 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 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 stricted area) will be less than 0.0001 mR/hr, as 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 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 ..
~!ASE DESCRIPTION I Shutdown and Preparatory Activities II Removal Activities III Installation Activities IV Post Installation and Startup Activities V Steam Generator Storage Activities SUBTOTAL Additional Tasks and Unassigned Personnel Categories PROJECT TOTALS TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
- STEAM GENlmATOR REPLACEMENT ACTIVITrns SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED LABOR EXPENDED
- EXPOSURE (MANHOURS) (MANHOURS) (MAN-REM) 39,021 142,76!1 596. 27 57,422 159,751 559.6 74,195 389,153 l1l18.23 62,650 90,502 427.54 300 3,659 35.0 233,588 785,829 2,066.64 ------85,814 -------233,588 871,643 2,066.64 Page l of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) 344.262 --602.335 748.324 179.230 5.054 1,879.205
- 261.427 2,ll,0.632
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TASK DESCRIPTION Erect Equipment Hatch Temporary Exposure Prepare and Load Test Polar Crane Open Equipment Hatch* De fueling and Fuel Storage Inst<1ll Reactor: Vessel Cavity Cover Installation of Jib Cranes TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LAROR ESTIMATED LABOR EXPENDED EXPOSURE (MAN HOURS) (MAN HOURS) (MAN-REM) 264 1,073 0.4 210 2,757 1.05 156 ------0.23 585 3,437 11. 7 130 2,385 1. 3 1,838 13 ,L105 9.19 Disassemble Manipulator Crane 58 1,501 1. 7L1 Install Steam Generator 572 7,527 2.86 Transport System Removal of Biological 1,296 3,959 19.44 Shield Wall Disassemble Shroud Cooling 150 918 3.0 *System Page 2 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) e,, 0.459 2.883 -------22.124 1. 972 14.822 ., 2.416 13.095 3.392 1.520 TASK DESCRIPTION Cutting of Crane Wall at !latch Opening Installation of Temporary Ventilation System Temporary Scaffolding Temporary Lighting and Power Cleanup and Decon Polar Crane Operator Shielding ll.P., Q.A. PHASE I SUBTOTAL TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SIIUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATTON -UNIT NO. 2 ESTIMATED LABOR (MANHOURS) 432 50 7,500 5,200 9,000 1,500 3,600 39,021 ACTUAL LABOR EXPENDED (MANHOURS) 1,379 14,559 6,609 17,216 1,368 21,930 31,286 142,764 l~STIMATED EXPOSURE (MAN-REM) 2 .16 0.05 75 26.25 135 4.5 270 32.4 596. 27 Page J of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) 1,.210 74.363 0.563 22.601 2.319 143.493 e TASK DESCRIPTION ADDITIONAL TASKS Installation of Service Air System Work Platform Modification Removal of Reactor Coolant Pump Motors Protection of Containment Components TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
- PHASE I-SIIUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED LABOR (MANHOURS)
ACTUAL LABOR EXPENDED (MANHOURS) 2,491 5,272 1,357 1,094 ESTIMATED EXPOSURE (MAN-REM)
UNASSIGNED PERSONNEL CATEGORIES Engineering Support Craft Support and Security Escorts Project Supervision and Administration Visitors and Inspectors Not Reported II II II Page 4 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) 0.670 0.181 4.621 4.054 5.657 10 .000 17.227 1.235 TASK DESCRIPTION SUllTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) PHASE I PROJECT TOTAL TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE I-SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED LABOR EXPENDED EXPOSURE (MANHOURS) (MANHOURS) (MAN-REM)
10,2]/, -------39,021 152,978 596. 27 Page 5 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM)
-* !13. 6L15 387.907 TASK DESCRIPTION
!{emovu L of l n s u la ti.on (lower shell, RC Piping) Removal of Insulation (upper TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II -REMOVAL ACTIVTT.rns SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR LABOR EXPENDED (MANHOURS) (Mi\NHOURS) 720 2,026 shell, 864 80 mainsteam and feedwater piping) Removal of Miscellaneous 72 5,424 Piping Set Up Steam Generator l, 152 224 Girth Cut Equipment Cut and Remove Steam 330 5,079 Generator Upper Shell Cutting of Reactor 2,982 20,235 Coolant Piping Cutting of Mainsteam and 1,428 2,838 Feedwater Piping Disassembly of Steam 792 10,791 Generator Supports Removal of Moisture 396 6,050 Separation Equipment Refurbish Steam Generator 9,246 21,756 . Upper Shell Page 6 of 15 ESTIMATED ACTUAL EXPOSURE EXPOSURE EXPENDED (MAN-REM) (MAN-REM) e-, 28.8 13.791 12.96 1.364 1.8 59.337 28.8 0.229 8.25 11.221 149.1 214.058 ---7.14 1.132 15. 8L1 49.021 1.98 6. 727 46.23 19.819 TABLE 1 PERSONNEL RADIATION EXPOSURI~
SUMMARY
PHASE II -REMOVAL ACTIVITIES SURRY POWER STATION -UNIT NO. 2 TASK DESCRIPTION Removal of Steam Generator Level Instruments and Blowdown Piping Removal of Steam Generator Lower Shell Temporary Scaffolding Temporary Lighting and Power Cleanup and Decon Polar Crane Operator H.P., Q.A. PHASE II SUBTOTAL ADDITIONAf, TASKS Material Handling, Equipment Maintenance, and Miscellaneous
- Construction Activities ESTIMATED LABOR (MANHOURS) 135 1,575 7,500 5,250 17,000 1,500 6,480 ACTUAL LABOR EXPENDED (MANHOURS) 2,311 3,859 11,969 6,071 26,731 1,308 32,999 159,751 30,991 ESTIMATED EXPOSURE (MAN-REM)
I~ .OS 31.5 75.0 26.25 85.0 4.5 32.4 559.6 Page 7 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) 7.671 29.875 46.464 5.910 83. 718 1.038 50. 960 602.335 53.897 TASK DESCRIPTION TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE II -REMOVAL ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED LABOR (MANHOURS)
ACTUAL LABOR EXPENDED (MANHOURS)
UNASSIGNED PERSONNEL CATEGORIES J*'.11g I n(!l! 1:1.ng Suppo1: t Cruft Support and Security Escorts Project Supervision and Administration VisJtors and Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) PHASE II PROJECT TOTAL 57,422 Not Reported II II II 30,991 190,742 ESTIMATED EXPOSURE (MAN-REM) 559.6 Page 8 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM)
Li. B58 l. 281 37.579 0.300 97.915 700.250 --.*:
TASK DESCRIPTION Steam Generator Lower Shell Installation Installation of Reactor Coolant Piping Steam Generator Girth Weld Installation of Main Steam Piping Installation of Feedwa ter Piping Installation of Blowdown and Miscellaneous Piping Install Steam Generator Level Instruments Installation of Insulation Temporary Scaffolding Temporary Lighting *and Power TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III -INSTALLATION ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR LAl30R EXPENDED (MANIIOURS) (MANHOURS) 1,926 12,696 6,768 90,695 5,400 41,853 3,735 12,9116 2,700 7,727 1,782 21,638 2,592 14,718 11,562 11, 562** 7,500 15,282 5,250 13 ,!1 91~ Page 9 of 15 ESTIMATED ACTUAL EXPOSURE EXPOSURE EXPENDED (MAN-REM) (MAN-REM)
---9.63 18.300 67.68 329.181 27.0 17.578 18.68 17.299 13.5 3.985 17.82 83.942 *--12. 96 18.496 57.81 57.810** 75.0 39.298 26.25 8.795 TASK DESCRIPTION Cleanup and Decon Polar Crane Operator H.P., Q.A. PHASE III SUBTOTAL ADDITIONAL TASKS Material Handling, Equipment Maintenance, and Miscellaneous Construction Activities TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III -INSTALLATION ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED LABOR (MANHOURS) 17,000 1,500 6,480 74,195 ACTUAL LABOR EXPENDED (MANHOURS) 58,820 3,205 389,153 38,739 UNASST.CNED PERSONNEL CATEGORIES Engineering Support Croft Support and Security Project Supervision and Administration Not Reported II II ESTIMATED EXPOSURE (MAN-REM) 85.0 4.5 32.4 448.23 Page 10 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM)
- 96. 704 1.252 5.5.684 748.324 18.999 5.783 1.390 79.628 --*
TASK DESCRIPTION Visitors and Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) PHASE III PROJECT TOTAL TAIILE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE III -INSTALLATION ACTIVITIES SURRY POWlm STATTON -UNIT NO. 2 ESTIMATED ACTUAL LABOR LABOR EXPENDED (MANHOURS) (Mi\Nl!OURS)
Not Reported ------38,739 74,195 427,892 PagL! I l of 15 ESTIMATED ACTUAL EXPOSURE EXPOSURE EXPENDED (MAN-REM) (MAN-REM) e---------0.329 -------106.129 Li48. 23 854.453 .... , ..... ', **..*.. , ..... , .* ,., .*. ,,., ,,,,,,,.,;.,, *.*. ,,,.,,.*1t***t***,,*,1
,,,,, ...* , .* ,,,1\>' ,:-.*-.. ..;..
TASK DESCRIPTION Install Biological Shield Wall Repair Crane Wall Opening Install Steam Generator TAJILI~ l PERSONNEL RAIHATION EXPOSURE
SUMMARY
PHASE IV -INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED LABOR EXPENDED EXPOSURE (MANHOURS) (MANHOURS) (MAN-REM) 3,240 1,499 16.2 4 73 336 2.37 9,000 37,251 90.0 Recirculation and Trans'fei:
System Remove Reactoi: Cavity 130 289 0.65 Cover Inslnll Renctor Cavity 2'10 8/17 1. 2 Coaming Reassemble Manipulator 1,176 1,016 23.25 Crane Remove Steam Generator 425 143 2.12 Transport System Reassemble Shroud 576 3,451 11. 52 Cooling System Uydrostatic Tests 75 2,324 0.38 Refueling 585 585** 11. 7 Page 12 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM)
- 0.997 0 .1,00 67.739 0.351 0:731 1.176 *-* 0 .187 11.520** 3.358 11.700**
TASK DE SCRIPT [ON Temporary Scaffolding Temporary Lighting and Power Cleanup and !)econ Polar Crane Operator Painting II. p. ' Q.A. PHASE IV SUBTOTAL ADDITIONAL TASKS TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PIIASE IV -INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR . ESTIMATED LABOR EXPENDED EXPOSURE (MANHOURS) (MANIIOURS) (MAN-REM) 7,500 2,726 75.0 5,250 2,269 26.25 17,000 10,711 85.0 1,500 1,009 4.5 9,000 9,000** 45.0 6,L180 17,046 32 .L1 62,650 90,502 427.54 Material Handling, Equipment
5,870 -------Maintenance, and Miscellaneous Construction Activities Page 13 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) e 7 .136 1.019 20.928 0.367 45.000** 6.621 --179.230 2.305 TASK DESCRIPTION TABLE l PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE IV -INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION -UNIT NO. 2 ESTIMATED LAnOR (MANl!OURS)
ACTUAL LABOR EXl'ENIJED (MANl!OURS)
ESTIMATED EXPOSURE (MAN-REM)
UNASSIGNED PERSONNEL CATEGORIES Engineering Support Craft Support and Security P~oject Supervision and Administration Visitors and Inspectors SUBTOTAL (ADDITIONAL TASKS & PERSONNEL CAT.) PHASE IV PROJECT TOTAL 62,650 Not Reported II II II 5,870 9~,372 427.54 . *::.:::*:*
ACTUAL l~Xl'OSUIU:
EXPENDED (MAN-REM) 0.805 0.794 9.812 0.022 13.738 192. 968 :::*::::::::::::**:
e--. e-. : . : : : ~-: ; '.
TASK DESCRIPTION Steam Gene nrtor Storage Act.Lv 1.t.lei; TABLE 1 PERSONNEL RADIATION EXPOSURE
SUMMARY
PHASE V -STEAM GENERATOR STORAGE ACTIVITIL~S SURRY POWER STATION -UNIT NO. 2 ESTIMATED ACTUAL LABOR ESTIMATED LABOR EXPENDED EXPOSURE (MANHOURS) (MANHOURS) (MAN-REM) 300 3,659 35.0 TABLE NOTATION Page 15 of 15 ACTUAL EXPOSURE EXPENDED (MAN-REM) 5.054
- 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. --
Not ll!!tl!t:tcd Includes nidloactivc liquid uuste generated during Unit No. l outngl!. 1:~1_1_1." .1:. 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 PAGE 1 OF 4 YEAR: __ ....;l'-'9c...:7....:c9
__
TABI.E 2 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
__ ______ (h) _ _Ila logl.~11!.1
- *------* **---------
1-1 "If I< A A *
- ______ , -1:12 __ ---* --A ---r .,.---__
- ___ -* ----_____ .l::.1-1)________
.. ----.* --:------:-------:----:-:=----_-_-
__ _____ 1=.u11_ ------*u----
- ____ ---~---* .-,.-----~I ____ J..=J..1'.l
________________
,1------1--*----,----*----
~ -___ _ *---rcn.a,'"" -~-------~~=--11-J~-----------------
:* --:-----: : -_-_-_ :~~:::::~::_-_-_,------, ____ ,,_!!_::.
- . ../.!U----------------H----fi------
1 1---,1<~---
- *-i, -----** ~-----!-----______ )(c,-] l'> *--------------------*--
---"----!1---,------1------1
--* -,.,------.--*---,---~t;!:::.!!_~1_11
__________________
** ___ --~---* L L ** --:.--*-*!------
K1*-ll5 ff w " ____ Kr::!} ----,.---* .-----.----1---,.-----,1
--1-------1
_____ Kr..::!!0, _____________________
,__::::=_-
___
- ___ =._-=._-_-*=:_-
__ -_-_. "' ;, ---1,------u------i Ar-t, I * * * '~ ----* ------------------------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 1'::;1.l11r1L;,,( Tol11l t\ct1vlty Curleu "-T,~1-:-1U-1.u,1,:10
_ l * .IOKIO _ J-:71l1*:=-2
_____ 1r*.~----~-~-~--:=----~-! -A-.¥----=---
4--.-~-=---~-=-=~.I (c) Date of 5hlp111e111.
nnd
- llnrmrnlI,
- ll11rnwel.l, llarnwell, llnr:1111<,l 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.
O-l0-79 9-25-79 10-9-79 8-17-79 10-10-79 8-'21-79 ()) 8-211-79 (!,) PAGE 2 OF 4 --
1.. 1.rq111u llEI.E/1:.ES
__ Vo.lure of Llquid to lliochai:ge Canal * *-* Not Octcctcil l11cludcs rndloactlvc ll<Juld uasll! generated
<luring Unit Ho. l outage. TA!ll.E 2 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 :. __ ---'l 9'-'7...a9
__ *----""~"" ....... ---.,_...,..._,, _________ . ._._ -----*-* .* n~1rnul.\u:L~-
_ .* u~ur.1t._
.... __ /\PHU, .. , __ .MJV\Y ... ***--* --~.1:!'!.1~.v~*-
_ Jm.v **-~. UIHTS --.r * * -,.-------*
- **-,;: --,,-. .. -...---. " Ll.ters -S:-971~rr---r.-,ml~ ~:-6lmrs--
1.IIE*lli l~llb 9.9JE+5 ------------*-------11-------1--':..:..:~c:......::_
** Air Id, . P/IGg _3_ Of t, * --
l l. AIRUORNE REI.EASES
___ -(l0llnlt1t,en,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 . ------*------
PAGE ...!!._ OF 1* YEAR '---'-I 9'-7'-C9'----
______ 1-111 ______________________ -"T.o,rn-6--
- -----.-----.-* " l.-1]2 * " -.-----* -.-----._* ____ --~-----______ l::J.JJ, _______________
H---*----1
- * -.---I< ...,.---. ____ ..J..::l)/1
___________________
,_ __ ,. __
- ____ , ___ .___ * * " __ ---1.=J_J'.j
__________________
*---*---
---*---**-*:~_-_-_-_-_-_-,;_*--*---=--=--=--=-*:.-::.=*======= " ---(c) Ga,ic,i *------------------------
____ Xc-l)J ----* -~p;~. J.001110 ,1 ---* ---r-----.~----*-~----*-~---
-_____ X!,.:: l.J),n _______________
l----11-~~~,,.--
11-----
X I ,c 1. 91,E+O * * *--,,_ -~ c>_ ------*---------
1---~---1--~----ll--,,-------l--,~---*J---.---- -----K r-ll51.11
.. ________________
- * * ----;,;;-------,,.---
--~.----!*-,.-----. * * " * * * .. " ---,.---* . ______ 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. ___ ._;~--~.:.~----...... -....... ,. ...... --. .. ~~-ro,,*-. --~---~---... ---'"*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 (t*) .June date of ahlpmt!Uln continued 6-25-79,6-26-79,6-27-19 2-27-7'1 J-U-7'1 J-211-7')
,]-12-79 (2) 5-lfr-79 6-11*-"/9 7-l)-79 2-20-79 J-Ll-79 )-28-19 4-14-79 5-19-79 Ci-lJ-79 7-16-79 )-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 (+) ----
Volume (gal.) Activity (Ci) * ** TABLE 2A --*** ., .... EFFLUENT RELEASE AND SOLID WASTE COMPARISON
SUMMARY
STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION -UNIT NO. 2 LIQUID EFFLUENTS Total Estimated Releases 2.3 X 106 0.344 Total Actual Releases 3.0 X 106 0.519 GASEOUS EFFLUENTS Estimated Release/Unit During SGRP Isotope (Ci) Actual Release During Unit No. 2 SGRP (Ci) Noble Gases Negligible Iodines 4.53 x 10-3 Particulates 3.12 x 10-3 Volume (ft3) Activity (Ci) SOLID WASTE 101.3 6.88 X 10-6 1. 32 X 10-3 Estimated Quantities 26,236 18.9 Total 1977 Liquid Releases 1.4 X 108 67.67 Average Six ~1onth 1977 Release/Unit (Ci) 7400 0.24 1.4 X 10-4 Actual Quantities 57,790 63.6 Isotope Fe-55 Co-60 Co-58 Ni-63 Cs-137 Cr-51 Cs-134 Mn-54 All Others Total
- TABLE 2B EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION -UNIT NO. 2 LIQUID EFFLUENTS Total Activity Released (Ci) 1.41 X 10-l 1.04 X 10-1 1.01 X 10-l 6.79 X 10-2 4.93 X 10-2 2.46 X 10-2 2.24 X 10-2 5.08 X 10-3 3.26 X 10-3 5.19 X 10-l Percent of Total Activity 27 20 19 13 10 5 -i I 4 I 1 1 100 Isotope *Noble Gases -----------
Xe-133 Xe-135 Total Iodines I-131 Total Particulates
Co-60 Co-58 Cs-137 Cs-134 Cr-51 Mn-54 Total , .. TABLE 2C EFFLUENT RELEASE ISOTOPIC DISTRIBUTIONS STEAM GENERATOR REPLACEMENT PROJECT SURRY POWER STATION -UNIT NO. 2 GASEOUS EFFLUENTS Total Activity Released (Ci) 99.4 1.9 101. 3 6.88 X 10-6 6.88 X 10-6 7.00 X 10-4 3.01 X 10-4 2.19 X 10-4 4.94 X 10-5 4.51 X 10-5 8,37 X 10-6 1.32 X 10-3 Percent of Total Activity 98 2 100 100 100 53 23 16 4 3 1 100