ML19212A239
| ML19212A239 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1979 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18130A530 | List: |
| References | |
| PROB-790831, NUDOCS 7909060239 | |
| Download: ML19212A239 (28) | |
Text
{{#Wiki_filter:.p i STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 2 PROGRESS REPORT - NO. 3 FOR THE PERIOD JUNE 1, 1979 THROUGH JULY 31, 1979 DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY b).'[1"/3 7 9 090 6 0'2j9
TABLE OF CONTENTS PAGE NO.
1.0 INTRODUCTION
PR3-1 2.0 OCCUPATIONAL RADIATION EXPOSURES PR3-2 2.1 General PR3-2 2.2 Evaluation of Exposure Data PR3-2 2.3 Description and Format of Exposure Data PR3-3 2.4 Conclusions PR3-4 3.0 APPLICATION OF ALARA PRINCIPLES PR3-5 3.1 General PR3-5 3.2 Temporary Shieldir.g PR3-5 3.3 Decontamination PR3-6 3.4 Training PR3-7 3.5 General Techniques PR3-7 4.0 RADI0 ACTIVE EFFLUENTS AND SOLID WASTE PR3-9 4.1 General PR3-9 4.2 Airborne Releases PR3-9 4.3 Liquid Releases PR3-9 4.4 Solid Radioactive Waste PR3-10
5.0 CONCLUSION
S PR3-11 TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents c.... di
PR3-1 SSGP 1.0 INTR 3 DUCTION This Progress Report contains information on the radiological effects of the Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 2, and the measures taken to maintain these effects "as low as is reasonably achievable" (ALARA), during the period June 1 through July 31, 1979. With regard to radiological effects, the major tasks performed dur-ing the reporting period involved installation activities and included: installation of the steam generator lower shelle, in-stallation of removed reactor coolant pipe sections, and the steam generator girth welds. Installation of the steam generator recir-culation and transfer system, as well as ongoing peripheral and llh support activities (including: temporary scaffolding, cleanup and decontamination, health physics support and project supe rvision) also contributed significantly to the total radiological effects assessed during this period. The report sections which follow provide an assessment of the occu-pational radiation exposure expended, the dose reduction techniques employed and their ef fectiveness, and the radioactive ef fluents and solid waste generated during the reporting period.
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PR3-2 SSGP 2.0 OCCUP ATIONAL RADIATION EXPOSURES 2.1 General Occupational exposure to radia tion may be conside red the major radiological effect of the SGRP. Thus, s1pificant importance has been placed upon providing an accurate assessment of the collective radiation 2xposure which is expended in performing each of the tasks involved. Estimates of these exposures were presented in summary form in Table 5.3-1 of the report entitled " Steam Generator Repair Program", dated August 17, 1977 and amendments thereto, hereafter referred to as the SGRP report. 2.2 Evaluation of Exposure Data The program establisnad to assess the actual exposures received during the repair effort has been designed to provide data which is compatible with the detail and format of the exposure summary pre-sented in Table 5.3-1 of the SGRP report. This design permits valid comparisons between the es timated and actual exposures for specific tasks. In general, the program utt11zes daily worker exposure data, as recorded by self-reading pocket dos ime t e rs , in conjunction with contractor supplied, worker task data to evaluate current manrem expenditures. The worker task data is standardized to a system of discrete work packages (called Engineering Task Assignments) which was developed during the project planning phase. The use of this system to categorize exposure related work for in-dividuals on a daily basis facilitates the process of compiling an accurate breakdown of the collective exposure expended on the many tasks involved. A more detailed description of this program. and O 4 "' # O s. s' .a.100Js
PR3-3 SSGP the basis for its design, was presented in Section 2.2 of Progress Report No. 2 for the SGRP. 2.3 Description and Format of Exposure Data Table I presents a summary of the occupational radiation exposure expended during the reporting period, the labor and exposure ex-penditures to date (i.e. from project commencement on February 3, 1979 to July 31, 1979), and the original estimated expenditures. The following comments are provided for clarification and should be considered when reviewing the data presented. (a) Additional tasks performed during the report period which were not listed in Table 5.3-1 of the SGRP report have been included in Table 1. S imila rily, exposures received by personnel per-forming functions not directly attributable to any one task have been listed separately. (b) The " Task Status" indications listed in Table 1 are intended to aid in the process of comparing estimated vs. actual manrem expenditures during the repair effort. For tasks indicated as "in progress", significant exposure related work remains to be performed and a realistic comparison is imp rac t ical . For
" completed" tasks, the manrem and manhour values listed in Table 1 can be considered to represent the major significant expenditures for those tasks, therefore valid comparisons are possible. It should be recognized, however, that factors such as field changes to procedures, dismantling of task related support equipment, localized work area cleanup, etc. may con-h tinue to contribute small amounts of additional exposure and labor to a task for some time af ter completion is ind icat ed .
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PR3-4 SSGP (c) The Phase Subtotals listed in Table 1 are calculated by a summation of values for completed tasks. Expenditures report-ed for " Additional Tasks" and " Unassigned Personnel Categories" are allocated to a particular phase based upon the major acti-vities being performed at the time they are incurred. Thus the Phase Subtotals also include these values for phases which can be considered essentially complete. This is the case for Phase I (Shutdown and Preparatory Activities) and Phase II (Removal Activities). For Phase III (Installation Activities), only one of the listed tasks was completed during the reporting period and thus the Phase Subtotal does not yet include the expenditures mentioned above. 2.4 Conclusions A review of the data presented in Table 1 of this report reveals that the total occupational radiation exposure received for tasks completed as of July 31, 1979 is approximately 9% belcw the original estimate. The significance of this comparison is somewhat d iminis h-ed due to the number of in progress" tasks which could not be included. However, the fact that no worker assigned to the SGRP has to date received radiation exposure in excess of applicable federal standards, and the exposure reductions effected by the techniques described in Section 3 of this report, illustrate clearly that the committment to maintain occupational exposures ALARA is being successfully applied to the repair effort, o a'4~ J .A. 2 op LJ X
PR3-5 SSGP 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General This section summarizes the specific dose reduction techniques employed during the reporting period. In general, the techniques described were Lnplemented prior to this period; however, their continued application and effectiveness have provided significant benefits (exposure reductions) to a number of tasks performed dur-ing June and July. k'here the available data permits, the following evaluations include a quantitative assessment of the manrem savings which can be attributed to the technique used. Additional informa-tion on the techniques discussed, and huv they relate to the over-all steam generator replacement activities can be found in the SCRP report. 3.2 Temporary Shielding The use of temporary shielding can be attributed with significant reductions in personnel radiation exposure for the SCRP. In the early stages of the p roj e c t , extensive shielding of piping and components within the lower steam generator cubicles was performed to provide these work areas with minimum radiation exposure levels. b'here possible, this shielding has remained in place throughout the repair effort. In order to minimize radiation streaming f rom the exposed reactor coolant pipe ends within the cubicles, specially fabricated bags filled with lead beads were placed inside the pipes. Activities involving work on this piping were thus performed in lower radia-tion fields. These activities consisted prima rily of pipe end a p ~< e ty
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PR3-6 SSGP refurbishment , and fit-up and welding of the removed pipe sections, and required a combined expenditure of approximately 130 manrem during the reporting period tas listed in Table 1 under "Installa-tion of Reactor Coolant Pip ing") . Radiation survey data indicates that shielding of the pipe ends was effective in reducing exposure rates for these activities by an average factor of 5, and can thus be attributed with an assumed savings of about 520 manrem. 3.3 Decontamination The decontamination of reactor coolant pipe sections which were removed from the primary system was completed during the last re-port period and a detailed assessment of this process was presented in Progress Report No. 2 for the SGRP. In that report it was shown that an average exposure rate reduction factor of 1,000 was achiev-ed for the pipe sections undergoing decontamination, and that the total expr:ure " cost" expended during this process was approximate-ly 41 manrem. Subsequently, these pipe sections were refurbished in preparation for reuse in the system. The labor involved in this task, although not reported separately from the total to date for installation of reactor coolant piping, has been conse rva tively estimated at 2,500 manhours for the reporting period. The estimate for the previous 60 day period was 2,000 manhours, and thus a total expenditure of 4,500 manhours is calculated for this task. Radia-tion survey data, upon which the reduction factor of 1,000 was based, has shown that without decontamination this task might have required working on pipe sections with average contact radiation n 3 .. 4 g , -
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PR3-7 SSGP readings of 5,000 to 10,000 mR/ hour. The resulting exposure to accomplish the task could therefore have reached 45,000 manrem. This projection is provided merely to illustrate the importance of the decontamination technique used and emphasize its contribution to the ALARA committment. 3.4 Training The installation of reactor coolant piping represented the major task performed during the reporting period with regard to occupa-tional exposure. While the shielding and decontamination tech-niques described earlier were ef fective in reducing the radiation exposure rates associated with this task, the use of mock-ups to train the wo rkers involved can be credited with providing reduc-tions in exposure times. Welders, pipe-fitters, riggers and laborers all received extens ive training in the activities to be performed by " dry runs" in full scale piping mock-ups. Completion times were noticeably reduced as the simulated activities were re-peated to naximize 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 attempt-ed here, however, the inherent benefits of reducing exposure times for this major task are of significant importance to the ALARA program. 3.5 General Techniques The more general procedures and practices which have been utilized during the reporting period to assure adequate control of occupa-o 4 .. 3 y ..y sJ.A. ( A d J
PR3-8 SSGP tional radiation exposure and to maintain this exposure ALARA are described briefly below. (a) Periodic work area cleanup and debris removal is performed to avoid buildups and maintain good radiological working condi-tions. (b) Piping, valves and other components which must be refurbished prior to reuse are removed from the containment to allow this work to be performed in an area where exposure rates are lower. A special refurbishment building was constructed for this pur-pose. (c) Other general techniques and programs which were previously described in Progress Report Nos. 1 and 2 have remained in effect during this reporting period and are listed here for completeness: (1) comp rehens ive Health Physics and training programs, (2) the " work package" concept for task preplanning and re-view, (3) the project photographic and video-tape documentation, (4) in-containment " rest area" utilization, and (5) contamination control operations and equipment. Although quantitative assessments have not been performed for these
" general" techniques, all have obvious value in contributing to the overall ALARA program for the steam generator replacement project.
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PR3-9 SSGP 4.0 RADI0 ACTIVE EFFLUENTS AND SOLID WASTE 4.1 General Radioactive liquid and gaseous effluents, and radioactively con-taminated solid waste generated during the steam generator replace-ment project are summarized in Table 2. A discussion of each cate-gory is given below. 4.2 Airborne Releases Airborne releases for the reporting period originated primarily from continuous ventilation of the containment during the repair activities. This is necessary to maintain a negative pressure while the equipment hatch is open. The continuous flow is processed through appropriate filter banks to minimize the concentration of airborne particulates released to the environment. Releases for June and July are seen in Table 2 to be consistent with those of the previous two months. No radioiodines or noble gases were detected and the particulates are comprised entirely of those nuclides with relatively long half-lives which would normally be expected at this stage of the repair effort. 4.3 Liquid Releases The composition of radioactive liquid ef fluents released during the reporting period is relatively unchanged from that seen in May. The major contributing nuclides are present at quantities which have remained consistent throughout the project, with the excep-tion of Co-58 which appears to be declining due to its short half-life. A notation has been added to page 1 of Table 2 to indicate those months during which a concurrent outage for Surry Unit No. 1 O g *
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PR3-10 SSGP may have contributed to the quantities of radioactive liquids re-leased to the discharge canal. This was necessary since a shared laundry facility is used for both units, and the disposal of laundry waste water continues to be the major source of these effluents. 4.4 Solid Radioactive Waste The disposal of contaminated paper waste, disposable protective , clothing and contamination control materials, and, to a lesser degree, structural materials and components not intended for reuse compriset' the major portion of the solid radioactive waste gene-rated during the reporting period. Shipment of the remaining packages containing solidified decontamination solutions g: aerated during previous periods was also accomplished during June. 3r7130
PR3-ll SSGP
5.0 CONCLUSION
S The following general conclusions are based upon the info rma t ion contained within this report. (a) Although some variations can be seen when comparing the esti-mated vs. actual exposure expenditures for ind ividual tasks, the total exposure (manrem) expended to date remains below the original es t imate 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 is being ef fectively implemented and applied to the steam generator replacement activities. b) Radioact ive liquid ef fluents have exceeded slightly the total release estimate for activity presented on page 9. A.5-5 of the SGRP report. The total volume released to date is 65% of the es t imatec total. This indicates that liquid effluent concen-trations are somewhat higher than originally ant icipated. It has also been noted that some contributions to the liquid re-leases reported have occurred due to the concurrent outage for Unit No. 1. Nevertheless, the total activity released to date continues to represent only a small fraction (less than 1%) of that normally expected during station operation. (c) Airborne releases of radioactivity remain well below the esti-mates provided in the SGRP report on page 9. A.8-7 and are not anticipated to reach those es t ima tes during the project. (d) Solid radioactive waste generated to date has exceeded the volume and activity est imates originally set forth on page 9.A.9-2 of the SGRP report. This is attributed to the increase O 3 a >. *"*'.? '}i-
PR3-12 SSGP in personnel assigned to the SGRP, and the expected subsequent generation of higher volumes of contaminated paper waste, dis-posable protective clothing and contamination control materials. e e a .' . I s a :
" A h!. I PACE L OF 12 PERMINNEl. kADI A ION EXPOSukE StrHMARY STEAM LENFRATOR HEPIACFHEhi ACTIVITIES - RFPoHT PERIOD 6/l/79-7/11/19 SUkkY POWER STAIl3N-l! NIT NO. 2 AtillAI. B ABOM ACTUAL EXPOSUkE ACTUAL EXPOSUME PilASE ESTlHATED EXPENDED F.ST!HA1ED FOR REPORTING EXi'EN!;ED STATUS PilAS E RAboK TO - DATE EXPOSURE PERIOD TO - DATE (C-COMPEE1E) l> ESC N IUION (MANiklVHS } (HANilotikS) (MAN-kiB) (MAN-R F M) (MAN-kVM} (I=lN PROCkESS) saaCOMPI.ETED TASES ONI.Yaen i Shutdown and Prepatatory Activities 39,021 149,604 596.27 2.331 383.892 C II kenueval Activities 57.422 189,448 559.6 12.723 697.422 C Ill Installation Activilles 1,926 6.396 9.63 6.804 !!.010 I IV Post Installation and Startup Activities 0 0 0 0 0 I V Steam Cencrator Sturage Activities 300 3,499 35.0 0.010 4.876 C PkolECT TOTAL.S (CumpletcJ Taska only) 98,669 348,947 1,200.50 21.868 1,'E7.200 (O
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T_A til E l. PAGE 2 OF _R PEkSONNEl. RADIATION EXPOSilkE SLRtHARY S1 EAM CI'.NERATok KEPI ACEHt uT ACTIVITI ES - kt PORT PER IOD 6/1/79-7/11/79 SUkkY Pot #R STATION-l! NIT No. 2 ACTUAL. LABOR ACTUAL EXPOStiRE ACTilAL EXPOStikE PilASE ESTIMATED E X P END'.D ESTlHATED FOR REPORTING EXPENI,ED S;A3US PliASE 1.ABOK TO - DATE EXPOSURE PERIOD TO - DATE (C=COMPl.ETE) DESCRIPTION (MANilotikS) (MANigS[ (HAN-l!EM ) (MAN-FEH) (MAN-REM) (l=IN PROCEESS)
* * *Al.i. TASKS COHHENtTD AS OF 7/ 3 lf 79 **
- I Shutdown and Prepara-tory Activities 39,021 149,604 596.27 2.331 383.892 C II kenu) val Activitien 57,422 189.448 559.6 12.723 697.422 C III Installation Actjvitles 74,175 198,393 448.23 309.276 385.093 I IV Pont Installation and Startup Activitles 14,444 24,217 134.54 41.134 43.733 I V Steam Generator Storage Activ-itses 300 3,499 35.0 0.010 4.876 C l'kolECT TOTAL.S (All Tasks) 185.362 565,166 1,773.64 365.474 1,515.016 U
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TAbt.E i PACE 3 0F 12 PERSONNEL. RADIATION FXPOSURE SilHMARY l'HASE l-StillTimMN AND PkEPARATORY ACTIVITIES SlikkY POWER STATION-t! NIT No. 2 ACTUAI. LABOR ACTilAL EXPOSllRE ACTil'.l. EXPOSUkE TASK ESTlHATED EXPENi>ED ESTIMATED FOR kEPORTING EXPENDED STAlllS LABOR TO DA1E EXPOSlikE PERIOD TO - DATE (C=COMPl.E X E) TASK DESCRIPTION (MANikH!hS) (MAP > CHS) (F AN-REH) (HAN-kEH) (HAN-REH) (l=lN PkOCRLSS) Erect Equipment lla tc h Temporary Enclosure 264 1.073 0.4 0 0.459 C Prepare and load Test Polar Crane 210 2,720 1.05 0 2.863 C O.23 ----- C Open Equipment liatch I56 -- -- (See Note 1) Detueling and Fuel Storage 585 3.437 11.7 0 22.124 C Install Reactor Vessel 130 2,385 1.3 0 1.972 C Cavity Cover Cutting of Pressurizer Cubicle Wall --- ---- --- - ---- (See Note 2) lustallattun of .llh I,838 13.1Il 9.19 0.879 14.667 C Cranes Disassemble Manipulator 58 1,501 1.74 0 029 2.416 C Crane Install Steam Generator 572 6,805 2.86 0.54 6 11.737 C Transport System Heninaval of blutoglia! 1,296 3.959 19.44 0 3.392 C Shle!J Ws11 Disassemble ShrouJ 4 I50 884 3.0 0 1.512 C Cooljug Systom C.0 h .,
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1AB1E I PACE 4 OF A PENSot4NEl. RADI ATION EXPOSilkE SilHMAkY PHASE I-SI:UTDtMN AND PHEPARATORY ACTIVITIES SUkHY P(MER STATION-UNIT NO. 2 ACTUAI. IAh0K ACTUAL. EX1'0SUNE ACTUAL EXPOSURE TASK ESTlHATED EXPENDED ESTIMATED FOR REPokTING EXPENDED STATUS TASK LABOR 10 - DATE EXPOSURE PERIOD TO - DATE (C=COMPl.ETE) DEfiRIPTION (HANilOU R S ) (HANiloilHS) (HAN-kDO (HAN-kFH) (H..N - N EM) (I=lN PPIM;HESS) Cuttlng of Crane Wall at ilatch Opening 432 1,379 2.16 0.011 0.446 C Installation ut Temporary Ventilation System 50 9,488 0.05 0.255 1.851 C Temporary Scalfolding 7,500 14,559 75 0 74.36) C Tes4purary Lightind and Power 5,200 6,609 26.25 0 0. 5f> 3 C Cleanup and Decon 9,000 17,216 135 0 22.t01 C Polar Crane operator 1,500 1,368 4.5 0 2.319 C Shielding 3,600 21,930 270 0.417 143.493 C li. P. , il . A . 6,480 31,286 32.4 0 33.584 C ADlitTIONAl. T ASKS Bustallation of Service Air System - - - - 2,491 --- 0 0.670 C Work Platform Hodiflcation --- - 4,958 ----- 0 0.064 C Removal of ke..ctor Coolant Pump tlutors -- -- 1,357 ----- 0 4.621 C U p., si [. . , cc Ci
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TAh!L I PACE 6 OF 12 PtkStWNFl k ADI ATitW4 LXPOSUkE SUMMAkT Pil ASE II - Ft th1V Al. ACTIVIT itS SUkkY SWf k ST ATION-4 HIT No. 2 ACill Al. IJbuk AC1LIAl. E1FOSUkE ACTUAL. EXPosukE TASE ESTIMATLD EXPE!JDLD ESTIMAILD FOR kEPOR11NG EXPLNb6D STATUS 1ASK LABOR TO - DATE EXPOSOkE PLkluD TO - DA1E (C=GiMPI ET E ) lit SClil PT I ON (MANil:HikS) 1MANik d!kS1 (MAN-kFM) (MAN-kFM) (MAN-k t M ) ( I = l N _P kilt.R LS S{ keasuva t of lusulat tuu flower shc!!, kC Piplug) 720 2,026 28.8 0 13.791 C Removal o! ins,ulation (upper bl. ell, mainst eam and radisatst piping) 864 80 12.96 0 1. 3r>4 C kemoval of Miscellaneous Piping 12 5,424 1.8 0.174 59.317 C bet Up Steam Generator Clith Cut E<lu i pine n t 1,152 224 28.8 0 0.229 C Lut on.1 Remove Steam Csnerator Upper Shell 130 5,019 11 . 2 5 0.845 14.221 C Cutting of Heactor Coolant Piping 2,982 20,223 149.! 0.0 16 214.04b c Cutting of Mainsteam and teedwater Paping I,428 2.818 7.14 0.126 1.832 C Dimasses.bly of Steam Generator Supports 792 9,600 15.84 2.227 46.213 C keem> val ul Molature Separation Equipment 196 b,050 1.98 4.13) 6./27 C kelutbinh Steam Cencrator Lipper Shell 9,246 21 bb5 46.23 4.69) 19.811 C N ,( . .. j FA EC A_
TAbiE I PAGE 7 OF 12 P&kSONNEl. HAblATION EXPOStikE SlMtARY PHASE 11 - ktM1V As ACTIVIT !!S SlikkY PtlWFW STATION-l! NIT s.0. 2 t,CTUAL EXPOStikE ACTUAL EXPOSUkE TASK ALat!AL LAbok 15TIMATED FOr e'EPORTING EXPENDED STATUS ESTIMATED EXPENDED
- 1. ABOR TO - DALE EXPOSURE PEk10D TO - DATE (C=Ct etPI E1 E)
TASK l>ESCkiPTION _ ( mNilotikS ) (MAN -ki N) ( Mall-ki M ) (MAN-ktM) (I=IN PhotkFSS1 iMANihWINS) kesm2 val of Steam Cenerator I.evel lustruments and Blow- 7.671 C down Piping 135 2.311 4.05 0.375 ken.sval of Steam Generator 29.875 C luwer Shell 1,575 3,859 31.5 0.114 7,500 l l ,9t>9 15.0 0 46.464 C Temporary Scaffolding Temporary 1.ighting 6,071 26.25 0 5.910 C and Power 5,250 17,000 26,731 85.0 0 83.718 C Cleasiup and Deion 1,500 1, 308 4.5 0 1.038 C Polar Crane Operator 12, *n9 32.4 0 50.9t,0 C H.P., Q.A. 6,480 ADDillONAl. TASKS , _ Haterial Handling, Equip-ment Maintenance, and Miscellaneous Constructson 0 53.897 N/A Acttvitles ----- 30,991 -- -- lfNASSIChtD PEkSONNEl. CAIFGORIES
----- Not keported --- - 0 4.858 N/A Engineering Support m, j ' 06 Cc O
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TABLE I PALE 9 of 12 PEkSONNti. RADIATION EXPuSUkE StiettAkY PitASE Ill-INSTALL ATION ACTIVITIES SUkkY PtMik STATION-ilNIT No. 2 ACTUAL IABok ACTUAL EXPOSUkE ACTUAL EXPOSUkE TASK ESilHATED EXPENbe_D ESTlHAIED FOR REPORTING EXPENDED STATUS TASK IAhok TO - DA1E EXP050kE PEkl0D TO - DATE (C=d eu't.ET E ) DESCkiPTION (HANilotlHS) JMANitot!kS) (f TAN-kt H ) (MAN-kEHJ (HAN-kEM) (l=lp FR(n.kESS[ Steam Generatur 142wer Shell Installation 1,926 6,196 9.63 6.804 31.010 C Installation of kcactor Coolant Piping 6, 7 t.8 58,295 67.68 129.901 193.247 I Steam Generator Girth Weld 5,400 28,267 27.0 4.7b9 !!.747 I Installation of Hain Steam Piping 3,735 2,I68 18.68 0.421 1.476 I Installation of Feedwater Piping 2,700 470 13.5 0.171 0.326 1 Installation of blow-1 vu and Miscellancoum Piping I,782 I,205 17.82 3.590 3.590 I Install Stcan G:ncratur icvel Instruncuth 2,592 15 12.96 0.021 0.021 1 Installation of Insulation 11.562 37 57.81 0 0.099 I Temporary ScalfoiJing 7,500 7,694 75.0 20.I13 20.113 I Temporary I.igleting
& lbwer 5,250 7.285 26.25 5.440 5.440 I C
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TA til E I PACE 10 OF 12 PikSuNNEL kADIA110N EXPOSUkE SUMMANY PilASE Ill-INSTALLATION ACTIVITIES SUkkY P(WFR STATION-UNIT No. 2 ACTUAL lABdk ACTUAL EXPOSUkE ACTilAL EXPOSURE 1ASK ESTIMATED EXPENDED ESTIMATED Fok kLPokTING LIFENDED ST A10S TASK IAbuk TO - DATE EXPOSURE PEkl0D TO - DATE (C=Q4tPI ET E ) DESCklPTION (HANih >Uk S ) Ot%hiloUkS) (MAN -k FM) (MAN-kFM) (MAN-kEM) (I=IN l'kOCitESS) Cleanup and Decon 17,000 27,377 85.0 4;.920 45.920 I Polar Crane Operatur 1,500 1,306 4.5 0.918 0.918 1 H.P., Q.A. 6,460 3 6, t.39 32.4 35.396 35.396 i Al>DITIONAI. TASKS Material llandling, Equip-ment Maintenance, and Hi nc e!!aneoum Const ruc t ion Activities ----- 21,244 -----
!!.666 11.666 N/A UNA!;SIGNl D PERSONNEL. CATEGORI ES Fugineering Support -----
Nat keported ----- 3.331 3.331 h/A Csaft Support and Security ----- ----- 0.451 0.451 N/A Project Superviaton and Administration ----- ----- 40.119 4 0. ! ! 9 N/A Visitors and inspectarm ----- ----- 0.223 0.223 N/A Sul,t o t a l 1% 3e 111 (Conepleted Tanns only) 1,926 6,396 9.63 6.804 11.010 O .. ] L4 as cs
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TAti! E I PAGE 12 OF 11 Pt kSONNt'I. RAI)l ATION EXPOSUkE SlitetANY PilASE V - STEAM CENERATOR STM AGE ACTIVITIES SUkkY PiaWEk STATION-UNIT No. 2 ACTUAL IABOM ACTUAL EXPOSURE ACTUAL EXPOSt%E TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PEul0D TO - IIATE (C=COMPIElk) liESCRIPTION (HANiloU N S ) (MANik)U W S) (HAN-REM) (MAN-REH) (HAN -S tJ4) (I=IN PROCkFSS} Stease Generator St orage Activities 300 3,499 35.0 0.010 4.876 C lAbtE NOTATION i
- 1. Labor and Exposure ex: sid i t u r e s for this taa.k were incluJed in other task totals. (Prim.arily "Defueling and Fuci Stoaage").
Labor and Exposure cat. .ites are included in the Suttotal Values.
- 2. This task was caiscellcJ Juee to equipinent changes. Isabor ai>J Exposure Est imat es ar e not included in t he Suttutal values.
N/A- Not Applicable. I. abor and Exposure Expenditures are included in the Sobtotal Values for Phases I and II. They cre not included in the Suttotal Values for Phase I!! (See Report Section 2.3.c). (.) 3.. () r
- ,[.A
TABl.E 2 SifRRY PtWER STATION PACE 1 OF 2 strAll CENERA1UR RErlArt'P1EleT FRO JECT RFFORT OF RADI0 ACTIVE EFFI.tll'.tOS Y tan t 1919 _
. . ~ . . - . - _ _ _ _ _ . . ~ . . _ .. ~ ...... , _ . . . ....... .. . ,,
I. l.IQUID REl. EASES ,
. _ . , .[EllitV681 , !,1$4Cl! .. .. , TI.l M m._ ._ tBY_ _, JtU,E, __ Jtit.Y (4t!TS -' ~ ~~;
Usrien ,, -- - - - - - - - _ _ _ _ _isotepes ReleascJ titC jici /mi
C UC-5 ^'
$IM j.[_10 ' 2.16E-5 4.62E-4 I _w ,,s 6
- l-1 12 8x 10-6 . . 7
_._ 1-1 M _ l71,30-l!C.3 m ' r . l
'- l_I n . .
4 x lii3 r ,r - g -l ls . . 7 . 142 E-3 _ .122}E-l _ bl* I N I 2 2Ol N' Co-l U 2x 10 ] ,11g!E.-j _ _.} 19 9g-]_ ,,_ _5.,p h 7.9 /E- 3 _6.2061-~ ~f.90E-3 -- -- Co-51 4 x 10- -}13tE-9 1t11E-6 3.00t C I 4.00E-6 Co-58 - ST16 ' ~ g tpr-2 11 d g-~ EUE!7~ 7. 90c- ) Tlot-3 1.6oE-1
- 1. 71E-T
~
__fM-60_ __h F 5 2.0162 9.09E-3 6. liiii 1 T TUE H 50E.) T 23El~ 1. )III 3 -'- - - - - - Hn-54 1 x 10-' l.2aE-3 3.42E-4 1 MFF 2.20E-4 lp I 1-'165~ 7 - -- a e . a Na-14 ) g
- 7. N -' 7 .W E-5 Cr-51 2 'al 0 ' ~5 350-) 6.48E-4 3. 4 t4F ) a fe-59 5x *
- 1. 3211- 6 * ~a 7 - - - ~ ~ ' - -
Ix~10-' 10 1
~ l.ME'l- 7
~
Ute -9 5 !.98E-4 8.8tE-5 ~5.60E-5 7./ut-> Sh-124 2x 10-I e ~3 2.10FI l. 401F 4 -~3 = ~ ' - ~ - Sh-125 1x 103 ' 'I'23E-4
- UTC 4~ C5iiaM - 7 ' --
In-65 1x 10 l!llE 5~' 4.06E-6 4. 70 t>- 5 - MUIIT-'- TUE I 1.30E-5 '--7
~ ~ - - -
- 7. r -9 5 6 x 10 4 1 0tE-6 a ~l . S ul-4 5. 2 tE:-5 * *
- ~ ~ ' ~
__ H t.9.9 4x 10-5. 1 92E-5 ,,7.48E-6 ~}. 91tF S * *
- 1 3 ltu-101 0 x 10-5 a
- T_. IE~E- 6 *
* ~3 - - - - -
l X"-l 11 Jx IO E 9.42E-5 1.19E-4
- 7 a
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._ An .l th S
- 2.06E-5 T2I!75~ ' I
_ _3.) xm.10. 10' l T U E!T ~ - 33 II
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Hi-6 ) 1. 46 E- 3 [] yg _ y_ re-55 8xIP 1.01E-2 1 11E-2 l2]$1F}I]
. 2'E- 1.88E-3 ** N ~ ~~'
2.15iE I ' ^" ~ ~
^
Cc-144 3 t }0-5
- 9.59E-6 ~5 5BE-6 - - -
'C35E-4 ~3 3 1 r ')9 = 3x 10-8 '
~
* 'GIE 6 TIIE-6 S.-I_kl___ __ _ __9 E.10-5
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~ ~
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~~
I IIDo El5HF 9.9)E65
*tu ru t arint O
Q * *.sut e .vulysis t result s ex>t yet. a nvimt f ann service o nbr. , Its si rn el l it , mulysin dita will le stinittal as a sigplewnt. ye to this tr1sirI. '** * *
- Inc i n. Ice Ri.11.nc t ive I.lquid We t e generated during #1 outage
% C C lps c -- [B O-W5 4
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r
ese TABLE 2 FACE 2 OF 2 ~ St'RitT l'OUER STA TInta STEAll (Tlar;RAIOR RITI.M.1 lit.itT l'RulEt*T RI.I'Oltf OF RAD 10ACTI VE Et tLift;NTS YEAR: Jg79
- 11. AIRRORNE REl. EASES
- . . ~ _ _ . ~....., ,... - . . ~ .. ... .
odiTs..,g. n a pmt,, , 3)w31,__,. _osm,,,, , , g ny . .,,
-..........,..l....Ir _.tg _ ,y)y ,,,,, ,,,,_i t ootojeg Rr. eanc<
g u t t g_ _(a) JAt t icultitta __,_ p.,g 3 s, a e
- 7 l '. )RE-6 1.7]E-5
~
a Cu:1N ._J 21rd___ _1.1 X - > __V*F 6 7 h -5 ~ G i-' L79E-5 n:21 3 dit;:L__ * * * ~' __ C" 8 _~' _. ._ __ O t9) E- L__ del]E1 _ __Jt M Lt L _ 6. 31c- 5 8.90E-6 l . 7 3t.-5 ( i.- 6o
- 1. htt-5 ' ~J3E 5_ _GE's 4,17 g1 _ ~6~01E-5 4.141>5
_ tin-vn __ * ~* " TF ~! TMET ~~_ _ ' ' . ' re_39 e a
- 3
- 4 (tQ ~tta logen '~
_ hU[ 6.88E-6 *
- T
* '~3 ~~
1 - 1 12 * * * * * '
. . . . . u
- __. 1- 1 M __
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, , , _, y _, ._.
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~~~(F) ilases T '
xe- t p 9.63E W -- 1:iinseo * -'3 -
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--- g g __ - l- ggio I r --* r .
g g , _, _., , _. . _ __
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r 1 - - - -
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, , , __., __., _3
____. _. Ar- K It-{ 0 __, , _, , _, _3 _. _ 111.140 L I 11 lA 11111Af!I 1 VIL WAS T E_ It I sells AI. _ _ _ (a) Total Amount Solt:I Waste 3 l'a r k a ge d Fr 1. (dE 6 ) 1.llE64 6.92Ee) 6.WiM 3 9.10E63 7.18Et3 (IT~t.s t l oo t ed ~ioUl Ac t t vi t y Curles '935~l -~~ TREtu 'l. Ibu l ~ ~7. 5ll;i G - 1.o3E61 6.48Eeo (c) D.it e o f Shi rnen t and B.a n nwe l l , Barnwell, llar msll, Ilar mil l, n.o rnwe l l , ' E AUw~e I C _D.Dcoaltlaa - .S.C S.c Ji & _ S.C. S.C. S C. F 6- M (4) *r-%.,5 _ ,,_ T'IT T '* ~~7*7 49-**~
~ - * * '"'
1-87-19,_ Y ...... , ..-.... . _ .. _ .. _ .. .,. _ _ .... 2-20-79 _ 3-6-19 2-22-19 l-7-19 3-19-79 4-9-79 5-11-79 la-7-19(1) 7-10-79 C3
- tint tr'tectot 3-28-79 4-12-79 (2) 5-16-79 6-8-79 7 -1 1-79
" (O hie d e M % m u % l u 2-27-79 2-28-79 3-8-79 3-11-79 3-2 8-79 4 N 5-19-79 6-11-79 7-16-19 Q 6-25-79,6-26-19,6-27-79 3 79 1-29-19 5';2 3- 79 (2) 6-14-79 7-18-79(2)
.h 1-15-19 3-29-19 4-22-79 5 7) (2) 6-15-79()) 7-20-19
; 5-29-7) 6-22-79 7-23-79 6
C ) 5- 30-79(2) g (('- 39 7-28-79 d..' i ggpW e f.,, as.-. Pu W )I adh I""""}}