ML18114A753

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Steam Generator Repair Program, Progress Rept 2 for 790401-0531
ML18114A753
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/02/1979
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18114A752 List:
References
NUDOCS 7907050289
Download: ML18114A753 (33)
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{{#Wiki_filter:STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 2 PROGRESS REPORT - NO. 2 FOR THE PERIOD APRIL 1, 1979 THROUGH MAY 31, 1979 RETURN TOD FILES,,.,- aiEACTDR DOCKfT DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY 'i 9070:$028"~ '.

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 3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General 3.2 Temporary Shielding 3.3 Steam Generator Water Level 3.4 Decontamination 3.5 General Techniques 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 CONCLUSION

S TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents PAGE NO. PR2-l PR2-2 PR2-2 PR2-2 PR2..:..5 PR2-6 PR2-8, PR2-8 PR2-8 PR2-9 PR2-10 PR2-12 PR2-15 PR2-15 PR2-15 PR2-15 PR2-16 PR2-17

1.0 INTRODUCTION

PR2-l SSGP This Progress Report contains information on the radiolo-gical effects of the Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 2, and the mea~ures taken to maintain these effects "as low as is reasonably achiev-able" (ALARA), during the period April 1 through May 31, 1979. During this reporting period, removal phase tasks pre-dominated although some additional work involving pre-paratory tasks was performed. Preliminary work commenced on several installation tasks also during this period. With respect to radiological effects, work performed dur-ing the reporting period involved the following significant tasks: decontamination and refurbishment of removed re-actor coolant pipe sections, disassembly of the steam generator supports, steam generator lower shell removal and storage, erection of scaffolding, and containment cleanup and general decontamination. The report sections which follow provide an assessment of the occupational exposure expended, the dose reduction techniques employed and their effectiveness, and the radioactive effluents and solid waste generated during the reporting period.

L 2.0 2.1 OCCUPATIONAL RADIATION EXPOSURES General PR2-2 SSGP Occupational exposure to radiation may be considered the major radiological effect of the SGRP. As such, this as-pect of the project underwent an extensive evaluation to provide realistic estimates of the amounts of personnel radiation exposure (manrem) which would be required to per-form each of the tasks involved. These estimates 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 pro-ject, a program was established to monitor and compile the actual exposure received by personnel during the perfor-mance of these tasks. This section discusses the imple-mentation of that program and provides an evaluation of the occupational exposure information compiled during the reporting period. 2.2 Evaluation of Exposure Data The program established to compile the necessary ex-posure vs. task information 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. evaluate current manrem expenditures. During the initial re-porting period for the SGRP (February 3 through March 31, 1979)

e* PR2-3 SSGP full implementation of this program was prevented due to unforseen problems in the collection of worker task data. A full description of these problems, and their effect on the exposure assessment for individual tasks was pre-sented in Progress Report No. 1 for the SGRP and is not repeated here. As a result of this experience however, several discussions were held to explore more effective methods for the collection of worker task data and thereby improve the process of determining task related manrem. The conclusions arrived at during these discussions, and the resulting modifications to the established program are described below. (a) The original program design called for contractor supplied "Activity Reports" to list, on a daily basis, the activity performed by each worker. To facilitate the compilation of this data, a previously established activity coding system was adopted to categorize the tasks involved. It was found however, that the level of detail provided by this system unnecessarily complicated the process of assigning daily worker exposures and presented problems in tracking discrete tasks to completion. (b) A somewhat less detailed system for categorizing exposure related work existed in the use of Engineer-ing. Task Assignments (ETAs). These task assignments were developed during the project planning phase

PR2-4 SSGP and establish discrete work packages for the performance of individual tasks. The ETA system provides a simpler and more general basis for assigning daily exposures, while still maintaining the required level of detail. Since an ETA also defines the procedures to be followed in accomplish-ing that task, a more reliable assessment of task status (i.e. completion date) should be possible. The reporting of worker task data by daily ETA assignment rather than activity code was thus implemented for this reporting period. (c) The program to compile and categorize manrem expenditures by daily task assignment requires the use of daily dose measurements recorded by self-reading pocket dosimeters. Although thermoluminescent dosimeters (TLDs) provide a more reliable measurement of radiation dose, it is im-practical to read these devices on a daily basis and thus they cannot provide dose information in the detail necess-ary for this program. To maintain an acceptable level of confidence in the daily exposure data used, checks are performed to assure that this data does not differ from that provided by TLD measurements beyond acceptable limits. It is also planned that, upon completion of the SGRP for Unit No. 2, the total actual manrem expenditure com-piled from individual TLD measurements will be determined to provide a final comparison point for these two monitor-

ing techniques. 2.3 Description and Format of Exposure Data PR2-5 SSGP Table 1 presents a summary of the occupational radiation exposure expended during the reporting period and the totals expended to date. The original estimates of exposure and labor expenditures are included for comparison. The follow-ing 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 re-port have been included in Table 1. Sirnilarily, ex-posures received by personnel performing functions not directly attributable to any one task have been listed separately. (b) The change in reporting of-worker task data for the assessment of manrem expenditures which was described earlier has necessitated a re-evaluation of the "task status" indications provided in Progress Report No. 1 for the SGRP. The adoption of an ETA basis for track-ing the listed tasks has in some cases broadened the scope of these tasks to include associated support and peripheral activities. As a result, some tasks which were considered completed as of the end of the last report period (March 31, 1979) have been charged with additional manrem and labor expenditures. The task status indications listed in Table 1 have been updated to reflect this change. It should be recognized that, although the ETA

PR2-6 SSGP system has provided an improved basis for evaluating the status of particular tasks, factors such as field changes to procedures, dismantling of task related support equip-ment, localized work area cleanup, etc. may continue to contribute small amounts of additional exposure and labor to a task for some time after completion is indicated. The manrem and manhour values listed in Table 1 for "completed" tasks can, however, be considered to repre-sent the major significant expenditures to be incurred by those tasks. (c) The Phase Subtotals listed in Table 1 are calculated by a summation of values for completed tasks only. 2.4 Conclusions The implementation of a revised manrem assessment program for this reporting period has rectified many of the pro-blems encountered in this area earlier in the project. The cooperation of many groups involved in the SGRP was necess-ary to effect this change and much improvement has re-sulted in our ability to document the radiation exposure associated with the performance of particular tasks. Continued cooperation is essential in maintaining and further improving this program to enhance its usefulness as a tool in evaluating job performance and exposure reduction and control techniques. It is important howe~er to focus on the overall objective of this and other programs relating to occupational radia-

PR2-7 SSGP tion exposure for the SGRP; that is to maintain this ex-posure, both to individuals and collectively, "as low as is reasonably achievable" (AI.ARA). The data presented in this report shows that totsl occupational exposure re-ceived for tasks completed as of the end of the reporting period is approximately 8% below the original estimate. Furthermore, no worker assigned to the Steam Generator Re-placement Project has to date received radiation exposure in excess of federal standards specified in 10CFR20. These facts confirm that the principle of AI.ARA is being effec-tively applied to the repair effort.

3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General PR2-8 SSGP This section summarizes the specific dose reduction tech-niques employed during the reporting period. The tech-niques discussed were, for the most part, implemented dur-ing the previous report period. The reductions in exposure rates achieved during that period however, have been effec-tive in minimizing personnel exposures for a number of tasks performed in April and May. In evaluating the effective-ness of these techniques, a quantative assessment of the manrem savings realized for certain appropriate tasks has been performed whenever possible. Additional information on the techniques described, and how they relate to the overall steam generator replacement activities can be found in the report entitled "Steam Generator Repair Pro-gram", dated August 17, 1977 and amendments thereto. 3.2 Temporary Shielding The placement of temporary shielding on piping and com-ponents located in the lower steam generator cubicles pro-vided significant reductions in the exposure levels associated with work in these areas. Radiation surveys performed prior to and after the installation of the shielding were described in detail in Progress Report No. 1 for the SGRP, and showed that for reactor coolant piping an average dose reduction factor of about 7 was achieved. Additional shielding of this piping was performed as

PR2-9 SSGP necessary to provide similar dose reductions for associated tasks performed during the reporting period. Using this reduction factor, an assessment of the exposure savings re-alized is possible. The manrem expenditure reported for installation of re-actor coolant piping was approximately 63 manrem. The work performed under this task for the reporting period involved primarily the preparation of removed pipe sections for de-contamination and the refurbishment of both the removed pipe sections and the pipe end openings within the steam generator cubicles. Pipe end refurbishment performed in the cubicles is estimated to account for about 40 manrem of the total 63 reported, and is that portion of the installa-tion task which has benefitted most directly from the application of shielding. The observed dose reduction factor of 7 thus translates into an assumed savings of about 240 manrem (i.e. (7x40)-40=240). Subsequent pro-gress reports will evaluate further "benefits" attributable to the application of this dose reduction technique, as re-welding of the removed pipe sections is accomplished. A final assessment of the "costs", in terms of manrem expended, will be performed upon completion of the in-stallation task and subsequent removal of the shielding. 3.3 Steam Generator Water Level The water in the steam generators wa.s maintained at a level covering the tube bundles until just prior to re-

moving the lower shells. The shielding effect of this PR2-10 SSGP water provided an approximate dose reduction factor of 10 for the area of the steam generator above the tubesheet. This factor was substantiated by actual survey results and can be used to assess the effectiveness of this technique for the three major tasks performed in this area during the reporting period. (1) Cut and Remove Steam Generator Upper Shell (2) Disassembly of Steam Generator Supports (3) Removal of Steam Generator Level Instruments and Blowdown Piping. The total exposure expended during this period for the three tasks was approximately 54 manrem. Using the ob-served dose reduction factor of 10, a postulated exposure savings of about 486 manrem can thus be attributed to the use of steam generator water level. During the previous report period, a savings of approximately 90 manrem was calculated for this technique. The total savings realized thus equals 576 manrem. Since practically no exposure "costs" were required to utilize this technique, its value in meeting the ALARA committment is obvious. 3.4 Decontamination The electropolishing process used to decontaminate removed reactor coolant pipe sections is described on page 9.C.3-1 of the SGRP report. During the reporting period, the

PR2-11 SSGP decontamination of all removed pipe sections was completed and radiation survey data collected prior to and after de-contamination has been used to evaluate the effectiveness of this process. Prior to decontamination, surveys revealed average contact readings of 5,000 to 10,000 mR/hour on the inside pipe sur-faces. Average contact readings after decontamination were nominally 1 to 5 mR/hour. Surface irregularities prevented one pipe section from decontamination below 30 mR/hour on contact, however, levels at the pipe ends, where refurbish-ment and welding are performed, were measured at 3 to 5 mR/hour. Based on these measurements, an average dose reduction factor of 1000 can be attributed to the use of the electropolishing technique. The exposure expended during the reporting period for pipe decontamination was approximately 30 manrem. When added to the 11 manrem re-ported for this task in Progress Report No. 1, the total exposure "cost" for reactor coolant pipe decontamination equals 41 manrem. Although only preliminary data is available at this time, an assessment of the manrem sav-ings which are expected to be realized as a result of this technique was presented in Progress Report No. 1, and some observations about that assessment can now be made. The projection assumed that about 6800 manhours would be required to reinstall the reactor coolant piping, and that this work would be performed in an average radiation field of 10 mR/hour. The projected expenditure to

PR2-12 SSGP accomplish this task thus equaled 68 manrem. Although the actual installation (welding) of this pipe had not yet begun during the reporting period, significant labor had been expended in refurbislnnent of the.pipe after decon-tamination. This work was not reported separately from other refurbishment performed on the pipe ends in the steam generator cubicles, but can conservatively be es-timated at 2000 manhours. Thus, without decontamination, 10,000 to 20,000 manrem might have been required to accom-plish this work. If the remainder of the installation task is accomplished within the estimated 6800 manhours, ex-posure savings attributable to decontamination could ex-ceed 80,000 manrem. Obviously, these numbers are theore-tical and are provided only to illustrate the importance of this technique as it applies to the repair effort and the ALARA policy. 3.5 General Techniques The more general procedures and practices which have been utilized during the reporting period to assure adequate exposure control and to satisfy the ALARA com.mittment are briefly described below. (a) General work area cleanup and debris removal is performed periodically to avoid buildups and maintain good radiological working conditions. Decontamination of tools, equipment and components is also performed when necessary to facilitate handling and transfer.

PR2-13 SSGP These efforts have resulted in cleaner and safer work areas and have minimized the potential for radioactive airborne contamination during the many removal acti-vities which were performed. The use of personal respiratory protection equipment has been required primarily as a localized precautionary measure during cutting and grinding activities but has not been necessary on a general basis. This situation con-tributes to improved worker efficiency and reduced ex-posure times. No instances of significant external or internal personnel contamination were identified during the reporting period. (b) The use of tents and glove boxes for specific cutting and grinding operations has been required in an effort to maintain low airborne contamination levels within the containment. Controlling the spread of contamination through use of this equipment also facilitates cleanup operations. Experience to date has shown however, that this technique should be evaluated on a case by case basis to ensure that an overall reduction in personnel exposure can in fact be achieved through its application. (c) Early in the project, "rest areas" were designat~d inside the containment to accomodate workers during idle periods*. The rest areas are located where ex-posure levels are minimum (less than 5 mR/hour) and are well posted for identification. When utilized

PR2-14 SSGP effectively, workers can reduce their exposure by spending work breaks, material and equipment delays, etc. in these low dose rate areas rather than stay-ing at the work site where dose rates may be signifi-cantly higher. Increased emphasis was placed on in-forming workers of the importance of this practice when it was observed that rest areas were not being used consistently by all personnel. During the re-porting period this added emphasis largely eliminated the problem and the rest area concept was successfully applied as an effective dose reduction technique. A number of additional programs and techniques which were implemented prior to this reporting period were described in Progress Report No. 1. These techniques continue to play important part in accomplishing the overall objective of ALARA for the SGRP and will remain effective for the duration of the project. They include: the Health Physics and training programs, the "work package" concept for task preplanning and review, special tool and equipment design for exposure reduction, and the project photo-graphic documentation. Although quantitative assessments of manrem savings have not been performed for the "General" techniques described, their value in maintaining occu-pational exposure ALARA is obvious and bears further evi-dence of our connnittment to this policy.

4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General PR2-15 SSGP Radioactive liquid and gaseous effluents, and radioactively contaminated solid wastes generated during the steam gen-erator replacement project are summarized in Table 2. A description of each category is given below. 4.2 Airborne Releases Airborne releases during the reporting period originated primarily from continuous ventilation of the containment during the repair activities, to maintain a negative pres-sure while the equipment hatch is open. This, continuous ventilation is processed through appropriate filter banks to minimize the concentration of airborne particulates re-leased to the environment. As can be seen from the data presented, the releases for April and May consisted entirely of Cs-137, Co-58 and Co-60. These isotop.es have relatively long half-lives and are those normally anticipated to re-sult from the repair of contaminated components in a light water reactor facility. 4.3 Liquid Releases The major contributor to liquid effluent releases attri-buted to the SGRP for this reporting period was the dis-posal of laundry waste water. The activities and relative distribution of the isotopes released during April and May are not seen to be significantly different from liquid

effluents generated during the two preceeding months, although a slight reduction in the number of isotopes de-tected during Hay is evident. In addition to the total curies of each isotope released, the volume of liquid waste discharged has been included in Table 2. 4.4 Solid Radioactive Waste PR2-16 SSGP The disposal of contaminated insulation, structural material, and piping and components not intended for reuse has comprised the major portion of the solid radioactive waste shipped during the reporting period. Solidified decon-tamination solutions have also contributed significantly to the volume and activity totals listed in Table 2.

e PR2-17 SSGP

5.0 CONCLUSION

S Based on the information contained in this report the following general conclusions have been made. (a) The ALARA Program originally set forth is being im-plemented and applied to the steam generator replace-ment activities. Improvements to this program are continually being evaluated to provide still further reductions in occupational radiation exposure. (b) Documentation of task related personnel exposure has been improved significantly and should permit (c) a more accurate and reliable assessment of this as-pect of the SGRP. The total exposure (manrem) expended to date remains below the original estimate established prior to commencement of work. (d) Radioactive liquid and gaseous effluents are still within the total release estimates presented in the SGRP report on pages 9.A.5-5 and 9.A.8-7, respec-tively; although liquid effluent concentrations have been higher than originally anticipated. These re-leases, however, continue to represent only a small fraction of those expected during normal station operations. (e) Solid radioactive waste generated to date has exceeded the volume and activity estimates originally set forth on page 9.A.9-2 of the SGRP report. This is attributed to the increase in personnel assigned to the SGRP, and the expected subsequent generation.of higher volumes

of contaminated paper waste, disposable pro-PR2-18 SSGP tective clothing and contamination control materials.

PHASE DESCRIPTION Shutdown and Preparatory Ac:tivities II Removal Activities [II Installation Activities IV Post Installation and Startup Ac:tJvitles V Steam Generator Storage Activities Pl({).JECT TOTALS (CompleLed Tasks Only) ESTUL<\\TED LABOR (HANHOURS) 39,02] 47,)84 0 0 0 PAGE I OF J l TABLE l P EllSOl!llEL lh!JTATIOH E:-:POSUUE Sin-L"tcl:Y STMM GENEllATOR REPLACEMENT ACTIVITIES - REPORT PERHJD 4/1/79 - 5/)J/79 SURRY POHER STATION-lJHIT NO. 2 ACTUAL UllOll EX!'ENIJED 'J'O D.<'-TE (Hl,WlOURS) ESTHL'\\TED E:,POS~,rn (WJl--*ltE:-1)

      • COMPLETED TASKS ONLYto,t, 147,724 596.27 152,496 1,97.5]

0 () 0 0 0 () ]00,220 109],80 LCTUAL EXPOSUTtE FOl{ :tE!'O},*l'lHG PERIOD (MAN-ltEH) 30.685 352.618 0 0 u ]83.)0] ACTUAL J:Xl'OSURE EXPD;JlED TO DATE (:t!AN-RE!~) 381.561 625.595 0 0 0 1007.156 PllASE STATUS (C=COHPLETE) (I=Itl PROGRESS) C l l I

II Ill lV V PHASE DESClllPTION Shutdown and Preparatory Activities Removal Activities lnsta llatiou Activities Post Installation au<l Startup Activlties Steam Generator Storage Activities Project Tasks (AL 1 Tuslrn) TABLE I PERSONNEL RADIATION EXPOSURE

SUMMARY

STEAM GENEHA'l'OR REPLACEMENT ACTIVITIES - REPORT PERIOD 4/1/79 - 5/]l/79 SURRY POWER STATION-1/Nl'l' NO. 2 PAGE __ 2__ OF c._ll_ ACTUAL EX!'OSIJHE PHASE EXPENDED STATUS TO DATE ( C=COMl' 1.E'l'E) ESTIMATED LABOR (MANllOURS) ACTUAL LABOR EXPENDED TO DATE (MANllOlJRS) ESTIMATED EXPOSURE (MAN-REM) ACTUAL EXPOSURE FOR REPORTING PERJOD (MAN-REM) (_~._IA_N_-_11_E_M.c.) ____ (c...I_.=_IN l'RO._G_ll_Es_*s-'* >~-----

  • i<*ALL TASKS COMMENCED AS llF 5/ 31/79**t, 39,021 147,724 5%.27 30.685

)81. 561 C 57,422 176,!0J ',59.6 /109.42:J 68/1. 699 32,091 31,979 194.3 75.817 75.817 l 14,019 2,332 132.42 2.599 2.599 300 3, 2811 35.o 11.866 4.866 I 142,853 361,422 J,517.59 523.390 ],1119.5112

ESTUIA'J'ED V,.SK l.ABOR l!ESCRTPTION (mNIIOURS) Erect Equipment Hatch Temporary Enclosure 26l1 Prepare and I.oad Test Polar Crane 210 Open Equipment !latch 156 Ile fueling and Fuel Storage 585 Install l{eac toi: Vessel Cavity Covet* 130 CuttJng 'of rre8Hurizcr Cul>lcle Wall Installation of Jib Cr..11ws 1,838 Di sa,rnemble Manlpul a tor Ci:an" 58 I nsta 11 Steam Gl!ut!rator Tnrnsport System 572 l{emoval of IUol.ogical Sh id J \\~all 1,296 Disassemble Shn111d Cool lng System 150 'l'Afll.fs I PER:mM-!EL R!.DIATIOtl IXL'OSl!RE ~Uh*'.i.l,Y

  • PHASE T-SIIUTDOWN AND PREPARATORY ACTIVITIES SllR1iY POT-mR S'i:K'l'TDN-lnTIT NO. 2---

ACTU..\\L LABOR AC'fUAL EXPOSURE EXP!:'.NDED ES'J'THATEll FOR REPOR'l'ING TO - DA'l'E EXPOSURE l'ERIOU (MANIIOURS) (MAN-REH) (HAN-REM) 1,073 O.li 0 2,720 1.05 2.102 0.23 3,L, 37

11. 7 0

2,)85 l.] 0.198 12,353 9.19 12.798 J,402

1. 7l1

() 6,319 2.86

9. 7l19 3,959 19.411 0.055 88/1 3.0 (J.070 PAGE _3_ OF 11 ACTUAL EXPOSURE TASK EXPENDED STATUS TO -

DATE (C~CO!*!?LETt'.) (!1AN-RE!-i) (I=HI PROGRESS) 0.459 C 2.863 C C (Se" Note J) 22.124 C

1. 972 C

(See Note 2)

13. 7!lll C

2.387 C ll.191 C ).392 C l.512 C

ESTI?*IA'fED T.;S!~ LAllOR 'l',\\.Bi.E l PERSONNEL RADIATlON EXPOS!li{F: Slih,-';_RY PHASE 1-SllU'l'DOHN AND PREPARATORY ACTIVITIES

snrnrrrumm-STA1'TIJN=TJNTTrro.

ACTUAL I..~BOR AC'l'UAL E'.!POSURE EXPEND@ EST:,MA'J'ED FOR lff P(;RTINC TO - DATE EXl'OSuRE PAGE t, OF 11 AC'.t'UP.L EXPOSURE TASK EXPENDEfJ STATUS PERIOD TO D,UE ( i>COH!'LE'i'E) (MANHOURS) (MANIJOURS) (M.A.tH:EM) (HAN-REM) (MAN-REM) (I~IN PROGRESS) _____ fl~F.=.S~CRTP'i'_IO"-"'t"--l _________

,.:;:=.,:=:;:.::..,_ ____ ~==::.:.:.:::.!... ____ ~~......:..:='-------~=:....:.:.:::.:L.-_____ __.:=::.:.....:.:.::~----.....-:~....c..:.:.....;..==:-~~---

Cut ting' of Crane Hall at llatch Opening lnstallatlon of Temporary VentJlntion System Temporary Scaffolding 'J'eu~orary Lighting ilnJ Power Cleanup and Decon Po l.ar Crane Opet*ator Sldcldlng 11.P., Q.A. AlllHTTONAI. TASKS Installation of Service Aix System Work Platform Mud if lea t Jon Removal of Reilctor Cool.ilnt 1'11111p Motors 432 1,355 50 9,162 7,500 14,559 5,200 6,609 9,000 17,216 1,500 l,]68 3,600 21,881 6,t,80 31,286 2,t,91 4,958 1,357 2.16 0.106 0.435 C 0.05 0.059 1.596 C 75 0 74.363 C 26.25 0 0.56] C 135 0 22.601 C 4.5 () 2.319 C 270

1. 318 143.076 C

32.4 ()

33. 58!,

C 0.6'.i6 0.670 C 0 0.08!1 C () t,.621 C

V,SK DESCRIPTION Protection of Con-ta irnncnt Components llNASSTGNEll PEltSONNEL CATEGORIES Engineering Support Crait Support anJ Security Escorts Project Supervision anJ Administration Visitors and Insvt:ctors Subtotal Phase I (Completed Tasks Only) ESTIHATED l.AllOR (HANl!OURS) ]9,021 'i',\\Bl.E 1 PERSONNEL RADlATTOtl E:Xl'llS!l!m _ _gn,(HXf!Y PHASE 1-SllU'J'llOHN AND PREPARATORY ACTIVITIES SLJ,l!(Y PQl.!EirS'I'F.J'IDN=11Nrrrm. ACTUAL LAilOR EXPENDED TO - DATE (MANl!GURS) 950 Not Reported 147,721, ES'l'IHATED EXl'OSUtrn (f.L*.N-REH) 596.27 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM)

3. 5 74 0

0 0 0 30.685 PAGE 5 OF ll. ACTUAL EXfOSURE TASK EXPENDED STATUS TO - DATE ( C=CO'..fPLETE) (HAN-REM) (I=rn PROGRESS) 3.842 N/A 5.657 N/A 10.000 N/A 17.227 N/A

1. 235 N/A 381.561

E.STIMATED ,_!_s;,: LABOR

--=-S(';'.':IPTIG~l (HA!lEOURS)

Removal of Insulation (lower,;hell, RC Piping) 720 Removal of lnsuiation (upper shell, main<iteam an<l 86ft radi,ater piping) Removal of Miscellaneous I' i.p ini.; 72 Set Up Steam Generator Girth Cut Equipment 1,152 Cut an<l Remove Steam Generator Upper Shell 330 Cutting of Reactor Cuo I.ant P.iping 2,982 Cuttini.; of Mainsteam an<l Feedwater p lping l,l128 Disassembly of Steam Generator Support,; 792 l(emoval of Molsture Separation Equipment 396 Refurbi,;h Steam GL!n-eraLor Upper Shel 1 9,24(, nBLE 1 PERSOriNEL RADIA'J.'IG:*: _ E:-:l'OS!TRE SmJ:-!,'.!lY 1'111\\SE TI - HEi-10'/J\\1, ACTlVJ.TIES sumu 1*GT!t.Jr"--S*{1~*r10:i-u1n:1* No. T ACTUAL U,DOll EX?ENDC:D ESTIMATED TO - D?.TE EXPOSURE {}!LHEOUR~) (HAll-[lJ'.!I) 2,026 28.8 80 12.96 5,373 1.8 224 28.8 4,476 8.25 20,211 149. J 2,782 7.JA 8,540 .15. 8l1 l, Jl16 1.98 15,067 l,6. 23 ACTUAL EXPOSURE FOR REPOP..'fl!:G PERIOD Orn*I-i~i"*f) 7.]Ol1 0 3.554 () 8.402 21.737 0.108 4l.6B7 2.594

15. llB FACE 6

OF 11 ACTUAL EXPOSURE TAS!*: EXFE!lD:oi:l ST.\\'I::s TO - DXZE (C>Cc*:-::*I.:,-:-:) (K\\!l-RE>:) (1.,,:; r:.. ~ :*:: :*;:s'i -------** lJ. 791 C

l. 364 C

59.163 C

o. 229 C

J0.376 C 214.010 C 1.006 C l13. 98b I

2. 59l1 C

15.118

1.

T/,BLE 1 PERSONNEL RADIATICl1110:POSURE SUH.'!ARY PHASE II - REMOVAL ACTIVITIES SURT< \\""TOBE!f-s'i'A'fTO!,l-UlHT NO. Z PAGE 7 OF 11 AC'i.'UAL LABOR ACTUAL EXPOSURI: ACTUP.L EXPOSURE TAS:~ ESTI}!ATED EX.PENDED ESTIMATED

FOR REPORTING EXPENDED S'l'XiTS E.SK Lo\\BOR TO -

DATE EXi'OSLiRE PERIOD TO - nxr;;: (C--co:2,.c:::::)

~I:~*:C:=S...,.C:..:.!'<.c.cic.aP...:T:..:I:..:0:..:.!1:....... ________

__:(:,_:}.:!A~N~lc:.:lO::::U~R~S~)L-____ ~(~Nc::,'-~N~li~O~U'.!:R~S~)~---~(HA!ii-R_i:'_.*l_) _____...,(_M_AN-R_i:_H~)-------(:..c...}!,AJl-RC!*_l) ________ (I_~_-1_.:; ??.~~,~~;~l__ _____ _ Removal of Steam Genera-tor Level Instruments and Blo\\Jdown Piping Removal of Steam Genera-Lor:' Lower She] 1 Temporary Scaffolding Temporary Lighting and Power Cleanup and Dccon PoJar Crane Operator H.P., Q.A. ADOITTONAL TASKS Matedal Handling, Equipment Maintenance, and Miscellaneous Construction Activities llNASS [GNED PERSONNEi. CATECORTES Engineering Support 135 1,575 7,500 5,250 17,000 1,500 6,480 2,149 3,760 ll,969 6,071 26, 731 l,]08 32,999 ]0,991 Not Reported l1, 05 31.5 75.0 26.25 85.0 4.5 32.4 3.858 29.761

5. 910 73.0lJ 1.0)8 50.960 5).897 7.296, 29.761 5.910 8]. 718 1.0]8 50.%0 53.897 C

C C C C C C N/A N/A

T.\\SK DESC!{T PTTO,l Cn1ft Support and Security Project Supervision and Administration Visitors and Inspectors Subtotal Phase 11 (Completed Tasks Only) ESTHL<\\TED LABOR (HANIIOURS) 47,384 e 'l'Aln.E l PERSONNEL RADIATION EXl'OSUids S!JH"!Af.Y PHASE 11 - REMOVAL ACTIVITIES SURRY POWER STATION-lJNIT lW. 2 ACTUAL LABOR ACTUAL EXPOSURE EXf-£Nll£ll ESTU!ATED FOR IH':P01fflNG TO - DATE EXPOSURE PERIOD (MANIIOURS) (MAN-REM) (HAN-REH) Not Reported 1.28]

37. 57'J II 0.300 I

152,t196 1197. 53 352.618 PAGE 8 or-* u ACTUAL EXPOSURE 'fl.SK EXPEND2ll STATUS TO - DATE ( C;CO:,fP LET£) (HAN-RE:-1) (I;JN PROGRESS) 1.281 N/A 37.579 N/A 0.300 N/A 625.595

ESTU:A'J'ED TASK LABOR Dt'.Sc:RIPTTON (MANIIOURS} Steam Generator Lower 1,926 Shell lnstallatlon Installation of Rteactor 6,768 Coolant Piping Steam Generator 5,400 Girth l~eld lnstallation of 3,735 Main Steam Piping Lnstallation of 2,700 Feedwater Piping Installation of Ins11lat:ioo 11,562 Subtotal Phase Ill (Completed Tasks Only) TABLE 1 PERSONNEL R.1.DL\\TTON EXPOSURE SU}fMARY P!IASE IT 1 - l NSTALLATION AC'J'IVl'l'IES -snmrr1'ffi.illR-S'YA'l'TmFTTflT'l'"T.O-:-Z-- ACTUAL LAllOl{ ACTUAL EXPOSURE EXPENDEb ESTHIA'l'l*'.D FOR REPORTING TO - DATE EXPOSURE PEltIOD (HANHOURS) (t*tAN-REN) (MAN-REM) 2,412 9.63 ,,. 206 17,083 67.68

63. )l1l1 11,17,6 27.0 6.958 1,117 18.68 l.055 162 l3.5 ll.155 29 57.81 0.099 P.'1.CE _9 __ OF 11 ACTUAL EXPOSURE TASJ'.

EXPENDED STATUS TO - DATE (C=CO~*Jl'LETE) (MAN-REM) o~rn PRGGRESS) 4.206 l

63. )4l1 I

6.958 I 1.055 I 0.155 1 0.099 I

TASK llESCRlPTION Install Biological Shield Wall Repair Crane Wall Opening Repair Pressurizer Cubicle \\foll Install Steam Generator Recirculation and Trans fer System ltemovu Reactor Cavity Covet* lteassemb 1 c Man.I pulator Crane S11hlotal Phase [V ( Comp l.u Ced Tasks OnJ y) ESTIMATED LABOR (MANilOURS) 473 9,000 130 1,176 TABJ.li I PER.SONtlEL RADIATION EXPOSURE SU~!l*!ARY PIIASE IV - POST INSTALLATION ANll STARTUP AC'l'IV I TIES

ORRY POWE!t STATION-UNI'I' NO. 2 AC'l'UAL I.AllOR ACTUAL EXPOSURE EXPENDED ESTIMATED l,'OR REl'OR'rING TO -

DATE EXPOSURE PERIOD (MANHOURS) (MAN-REM) (MAN-REM) 102

16. 2 0.074 18 2.37 0.005 2,177

'JO.O 2.486 30 0.60 0.030 5 23.25

0. O(J/1 PAGE 10 OF 11 ACTUAL EXPOSURE TASK EXPENDED STATUS TO - DATE

( C= CO'.*IP LETE) (}L.\\N-REM) o~rn l'RGGRESSi 0.071, I 0.005 I (See Note 2) l 0.030 l

ESTil-L".TED e 'J'AHLE l PERSOHNE!. RADIP.TIOll _EXPOSURE SUNi*!ARY PJJASE V - STEAM GENERATOR STORAGE ACTIVITIES illffiY-PeiJER STATION-UNIT NO. 2 .ACTUAL LABOR ACTUAL EXPOSURE EXPENDED ESTUL\\'l'ED FOR l<E:*Oll'l'ING PAGE ~l_l_ OF ~L_l_ ACTUAL EXPOSURE L\\Sr: EXPENDED STATUS 'L!.SK D!::~CHTPTI0:-1 LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=CO:-IPI.ETE) Steam Generator Storage Activities (MANIIOURS) JOO (MANHOURS) 3,284 (MAN REN) 35.0 'l'AllLE NOTATION (HAN HEM) (~!t,ll REH) (I-IN 4.866 ,,.866

1.

Labor and Exposure expenditures foL* this task were included i.11 other task totals. (Primarily "Dcfueli11g and Fuel Storage"). Labor a11d Exposure extimates arc included in the Subtotal Values.

2.

This task was cancelled due to equlpment changes. Labor and Exposure Esttmates ace not included in the Subtotal values. N/A - Not Applicable. Labor and ExposuL*e Expenditures are included in Lhc Subtotal Val.lws. PROC[1ESS) l

l.

LI QII [I) IIEI..EASES CtJries TAUI.E 2 SIIRllY l'OWEII STATIOII STEAi! r.rmrm,\\'mn nr.1'r.Acr.ri1rnT rno.JRCT llEl'OllT OF llAlllOACTJ.VE F.FFl.111:rfl'S Yr.An:

    • --*-r,;~;topc:i Rciear;ed lll'C

.i!..Cl/ml ---i-~J)1 --- -------3-~J.O:-,--------* ----

2. 76E-5

-,,-. G-,2-E-, _-,,-- 6*. 2DE -~------ PAGE OF 19 79 J-l:)2 8 X 1()--6 -,;----- -vr-----* ------ *-------*- --*-------- 2 .. __ 1.--Ll:J _________ l __ x 10-r* 1--J.](, 2 X J.0-~ f--.1:J'j It X j(l-T,- it ---y C:l-J)lo 9 x tu=- . J,2.lE--3-- 2.2]E--J--. 2.4.lfl-j ~1-.-3-!:,J-i--3----- Cn-lJl 2 x 10-"!i-* Tit,E-J 5.90E-J 5.82E-3 -J.97£-j*-- -------

      • Co-57-*

4 **x 10--='1. S.54E-6 ___ 1. 71E-6 __ -9.mffi:s"- _____ _(}~-~~--------*----~~_!0=: _______________ 2. 351~-2 _LlSE--2_ ~m-r- .,.90E-L ________________ ---------- -- * ---~~~t-:frQ ___________ J_JLlll.=: 2.0JE-2 9.09E-3 J... 721:}-~ 6.lUP.-] ... (!!*:-.~~-----*---- _.. !. x 10--'* l.28E-J J.42E-4 1.J2E-iJ LJiIB:y- ------ ------ ---------* .. Na-7.f, - J -x-Iu-;- I. IOl'l--5 .. __ c,:-51 _________ 2 x 10-- 1

  • ---* *--- s-:SSE=-1~-

6.48E-fo 3.40E-J -- -r::ru!FT-- ---- Fc-'i9 5 X 10--'S

1. 42El-6

.. ;ij,::.95 ---------*--i:--;1(1::li 1.981H,

8. BJE-5 232E-4 *

. **-s1,::.121i----------z-;-10:::, ,\\ -:tToiFr-I. 40EJ-4

  • -- :;1,..:J 25
l. x 10::,;
  • ---- -l.2JE-4 -- -:,;---- ---i-:rm=l-4.50E-5

_-__ f(!:-lis

  • 1 x 10-'*

r:1IE-) ,,.o6E-6

4. 10EJ-s

-~:-u,~- --*---- *-------- ------------- zr-9'i-6 x w-*., -7.0lE-6 1.54(,J-4 5.20E-5 .. llo-n t,~ *Lo-5 5.92E-5 1.1,1m-(, 2.94B _* ______ *------* *------- ------- -** . ** Hu-J.03 8 X 10-5 B

  • Xn-1))
)-x 1o-=r-9.4~_ --

l.l<JE--4_ -,.---- --.----- ------* *--------- --------*- ,--~~ A1*.-l.ll>1n _________ l.x...J1J**.5

~ :----

,\\ 2.6611--5 l.24E-5 Nl-f,] J x J.o** 5-J.l16E-J t:-TIE:-J" 2.98El -u;---- ------- *-----*--*** **------** Fr.-55 8 K 10::.. l.07E-2 ____ 6.lJE-2 _ l.25E-2 ___ ** ---- ('p-ll1t, 1 10-s -/c 9.59E-6 2.15EJ-6 r--- --.;.~-*1<Jn..===-=-=-1_: 10:- 3 ,_ __ --;.---- 1--:--1s~ -~--- ___ Cc-_lt,1. ____________ _!J __ x __ 1u-s

  • ___ T.7iI~ -i-

. =--=--=-= *=--==--=- ~=_.'._=~: __

  • Vo.ltmn of Liqui.cl to Disdiafge Canal
  • I lot rietecto:l
  • *flampJ e nrwl ysis resuJ Ls not yet n'r.ei ved fr.om r;er.v.i.ce,Ji~nrlor.

l~on rrcP.ipt, i1llilJysis claw wi.11. be sli,mitte<.1 as il mq1pl('J11E11t to Lh.i s n'f X)J: L. J

e II. t\\IHIIORME REI.MSES TAIILE 2 Sllltl:Y l'Olllm STt\\TJOH STCl\\11 cr;mrnATOll HEl'I.AClil!EtlT PHO.JECT HEl'OllT OF ltAllIOt\\CTIVE EFl'LIJENTS PAGE 2 YEAR: ___ I <J /9 ----- ___ (I,) _llnJ01:c11~ __________________ _ 1-131 6.88E-6 1-J.]2 .~ ________ l-l)J _________ ----------- --- ______ 1-u1i_ ______________________ -- '~ _____ r-iu________ --{ cJ-<:nr:c:; --------------- ______ Xe-lJJ __ _ 9.6t,EH J.OOEl*O

-- '/(-----

-,r-

Xr:-l_J]n,_

-- ---- --l."~1EIO _____ Xc-1.35____ ________ Kr-115m____

  • --- *--- ---7,---

--r------- Kr-85________ r--~- ~---* . *-=----=== =--==---=:-=~ ----------* _______ Kr--117___________________ ____ ~--- _,;_____ _ :

  • ----*---x~P.i-----

---r--** --r-J.11 *. S.OJ,llLltfl.lJL<lA!~Il'aU./ASTILlllSl'.OSAI~- ___ ----- ------- ------* ------- -----

(:i) Tot;il t\\111n1111t SoU,I W:1ste P:1t*.lu-.r,e<I

  • {hJ l\\:;tl1nr11c<i Tot;il Actlvity (c) Date of m,Lprnent m11-,--'-----

________ lll.r;pnsltlon -------- FT 3 l.65El*J J.11E~~ 6.92~13 Curles 9.91,E-.l 3-;-f hR-1 u --- ""2.:--7!,IDT-lln rnwrd. I., lln rnwe 1..1, llarn,ie] I, _______ s.._c.___ _ _s_~t:. ____ s. c. ___ _ 6.601'11) 7.5Jmo Barnwo.Ll, s.c. ... *****,, __,_....,,.. ~--......, -**-- rT2.::20..:.79 *- -j.:;:;;_;79' "j.:jj:~79" '1-f;:.7fl4j *~-~79~ * * ~... ~,

  • Not IJetP.Ctecl 2-22-79 1-7-7'1 J-19-79 i\\-9-"/'J 5-11.-79 2-27-79 l-11-79 1-211--79 i\\-.12-79 (2) 5-Hr'79 2-2fl-7')

]-IJ--7 11 )-211-79 i\\-l.'1-79 5-19-79 1 711 1 79 i\\-17-79 )-15-79 ] 79 i\\-22-79 5'-i23-'79 (2) 5-25-79 (2) 5-29--7') 5- )0-1'1 (7.) 2 I I

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