ML18139B209

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Radiological Progress Rept 3,Jan-Feb 1981.
ML18139B209
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/31/1981
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139B208 List:
References
NUDOCS 8104020152
Download: ML18139B209 (32)
v • d • e


Text

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STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 1 RADIOLOGICAL PROGRESS REPORT - NO. 3 FOR THE PERIOD JANUARY 1, 1981 THROUGH FEBRUARY 28, 1981 DOCKET NO. 50-280 LICENSE NO. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY

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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 and Observations PR3-4 3.0 APPLICATION OF ALARA PRINCIPLES PR3-5 3.1 General PR3-5 3.2 Containment Cleanup and Decontamination PR3-5 3.3 Temporary Shielding PR3-5 3.4 Reactor Coolant Piping PR3-7 3.5 Temporary Containments and Ventilation PR3-7 3.6 General Techniques and Practices PR3-8 4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR3-10 4.1 General PR3-10 4.2 Airborne Releases PR3-10 4.3 Liquid Releases PR3-10 4.4 Solid Radioactive Waste PR3-10 TABLES Table 1 - Personnel Radiation Exposure Summary Table 2 - Report of Radioactive Effluents I

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PR3-1 SSGP

1.0 INTRODUCTION

The Steam Generator Repair Program (SGRP) for Surry Power Station, Unit No. 1 commenced on September 14, 1980. This third progress report for the Unit No. 1 SGRP contains information on the radiolo-gical effects of the repair effort, and describes the measures taken to maintain these effects "as low as reasonably acheivable" (ALARA), during the period January 1 through February 28, 1981.

With regards to radiological effects, the major tasks completed during the reporting period involved installation activities. These included the starting of reactor coolant pipe welding, and fitup and welding of the upper shell to the lower shell.

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. Throughout this progress .report and those to follow for the Unit No. 1 SGRP, reference will be made wherever appropriate to the progress reports issued during the Surry, Unit No. 2 SGRP for purposes of compari-son, and to identify differences in the replacement activities which have a significant effect on the radiological impact of the program.

e PR3-2 SSGP 2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General Occupational exposure to radiation is considered to be the major radiological effect of the SGRP. As such, this aspect of the pro-ject underwent an extensive evaluation during the planning phase to provide realistic estimates of the amounts of *personnel radiation exposure (manrem) which would be required to perform each of the tasks involved. These estimates were based upon the anticipated labor requirements (manhours) and the average radiation dose rates in the work area, and were presented in summary form in Table 5.3-1 of the report entitled "Steam Generator Repair Program", dated August 17, 1977 and amendments thereto, hereafter referred to as the SGRP Report.

Prior to commencement of the project, a program was established to assess the actual exposures received by personnel during the repair effort. This program was designed to provide data compatible with the detail and format of the exp<>sure summary presented in Table

5. 3-1 of the SGRP Report, thereby permitting valid comparisons between estimated and actual expenditures.

2.2 Evaluation of Exposure Data The exposure assessment program referred to above is 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-ditures. 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 individuals on a daily basis facilitates the process of compiling an accurate break-down of the collective exposure expended on the many tasks involved.

  • PR3-3 SSGP

-2. 3 Description and Format of Exposure Data Table 1 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 September 14, 1980 to February 28, 1981), 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 effort which were not listed in Table 5.3-1 of the SGRP report have been includ-ed in Table 1. Similarily, exposures received by personnel performing 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 may remain to be performed and a realistic comparison may be impractical.

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-tinue to contribute small amounts of additional exposure and labor to a task for some time after completion is indicated.

(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 Cate-gories" are allocated to a particular phase based upon the major activities being performed at the time they are incurred. Thus, the Phase Subtotals also include these values for phases in which a majority of the tasks have been complet-ed. This is the case for Phases I and Ii (Shutdown and Preparatory Activities and Removal Activities). For Phases III and IV, The Phase Subtotals do not yet include the expen-ditures mentioned above since a majority of the tasks have yet to be commenced and/or completed.
  • PR3-4 SSGP 2.4 .Cqnclusions and Observations As of the end of the reporting period, the SGRP for Unit No. 1 has been in progress for approximately twenty four weeks. It is becom-ing apparent at this point in the outage that less exposure is being accumulated in comparison to the Unit 2 outage. This is
  • attributable to a num!,er* of factors. Many of the workers and super-visors are the same ones that performed the work on Unit 2 so they-are familiar with the work. In addition steps were taken in the preparation for the Unit 1 outage to eliminate problems encountered in Unit 2 and to stream line the procedures. A comparison of the exposure attributable to reaching the same milestone events in Unit 2 that have now been reached in Unit 1 shows that Unit 2 took about 1600 man-rem to reach approximately the same point that Unit 1 took 1061 to reach or a savings of about 539 man-rem. It also should be noted that these milestones were reached in Unit 1 about 45 days earlier than in Unit 2.

3.0 APPLICATION OF ALARA PRlNCIPLES PR3-5 SSGP 3.1 General This section summarizes the specific techniques and practices which were employed during this reporting period in order to maintain occupational exposures to radiation "as low as reasonably achiev-able." (AJ;.ARA). Where the availa~le da.ta pe~nii ts, th_e. follo~ing evaluations include a quantitative assessment of the manrem savings which can be attributed to the technique used. Additional infor-mation on these techniques and how they relate to the overall steam generator replacement activities can be found in the SGRP Report.

3.2 Containment Cleanup and Decontamination After shutdown and the removal of all fuel from the reactor, a general cleaning of the containment interior was performed to remove loose radioactive contamination in the work areas and there-by reduce the potential for airborne contamination during subsequent activities. Where appropriate, removable floor covering (plastic sheeting) has been applied to facilitate additional cleanup during the repair activities. A special work crew has been. retained to continuously clean the work areas and to perform equipment deconta-mination. This effort will maintain optimum radiological working conditions and avoid buildups of debris.

While it is not possible to quantify the exposure savings attri-butable to this, technique, the benefit of maintaining effective control of contamination is seen in terms of its contribution to minimizing the overall hazard associated with the SGRP.

3.3 Temporary Shielding The use of temporary shielding resulted in significant reductions in personnel radiation exposure during the SGRP for Unit No. 2. A separate work package was devoted to the design and installation of this shielding, with particular emphasis placed on the lower steam generator cubicles where radiation levels are highest and several major removal and installation activities are performed. While the temporary shielding applied to these areas in Unit No. 2 was sue-

  • PR3-6 SSGP cessful in minimizing exposure rates for subsequent activities, the task of installing the shielding requir.ed a significant amount of exposure (approximately 143 manrem). In Unit No. 1, the benefit of this previous experience and the use of personnel with specific expertise in the installation of lead shielding has resulted in a considerable reduction iii the time and exposure incurred for this task. As seen in Table 1, the shielding performed thus far during the SGRP has totaled 60 man-rem. Additional shielding will be installed during the removal and installation phases; however, the major portion of this task with respect to its exposure "cost" has been completed. Detailed radiation surveys, performed prior to and after the installation of temporary shielding, have been used to assess the effectiveness of this technique in providing net reductions in personnel exposure for two of the major installation activities commenced during the reporting period.

(a) The fitup and welding of the reactor coolant piping was start-ed during this reporting period and has now totaled approxi-mately 71 manrem. Lead shielding resulted in a dose reduction factor of about 6 as described in PR2 which results in a total calculated exposure savings of 355 manrem.

(b) The installation of miscellaneous piping and steam generator instrumentation has resulted in the expenditure of 24 manrem to date. Lead shielding resulted in a dose reduction factor of about 5 as described in PRl which results in a total calcu-lated exposure of 96 manrem.

The assessments described above represent a major portion of the overall benefits expected to result from the application of temporary shielding techniques during this reporting period. All of the removal activities have been completed at this time. There are however, installation activities still to be performed which will benefit from.the shielding already in place. Subsequent pro-gress reports will provide further assessments of the "benefits and costs" of this ALARA technique.

3.4 Reactor Coolant Piping pR3.:.7 SSGP In the Unit No. 2 outage the old reactor. coolant pipe was decontam-inated and reused. In Unit No. 1 new reactor coolant pipe elbows were purchased. This resulted in the savings of 42 manrem which is attributable to the decontamination effort. In addition in the Unit No. 2 outage, three (3) sections of reactor coolant piping were removed from each loop. Based on experience gained in°Unit No.

2, it was determined that it was possJble to remove only two (2) pieces and still be able to achieve an acceptable fit up. This will result in a reduction of dose for the task of rewelding the reactor coolant piping.

3.5 Temporary Containments and Ventilation To a large degree, the inital containment cleanup and decontamina-tion has minimized the need for extensive use of temporary contain-ments such as tents and glove boxes to control the spread of conta-mination. In areas where significant cutting and grinding work must be performed on highly contaminated piping and components, however, temporary containments have been constructed and are being

.effectively utilized.

The most significant application of this technique has been made in the lower steam generator cubicles, where the removal of reactor coolant and miscellaneous piping is performed. In Unit No. 1, the lower cubicle for each steam generator has been totally enclosed to transform the entire room into a single containment. Portable ventilation units continuously draw air from these enclosures through appropriate filters whenever cutting or grinding operations are in progress. Personnel working inside the cubicles are.requir-ed to wear respiratory protection equipment during these opera-tions, and until the ventilation flow has effectively reduced the airborne radioactivity to acceptable levels.

Additional tent enclosures have been constructed in various loca-tions to provide controlled work areas for pipe cutting, component refurbishment and equipment decontamination. Portable, filtered ventilation is provided to these enclosures as appropriate.

  • PR3-8 SSGP The benefits observed to-date for these ALARA techniques are three-fold.

(a) The use of small glove boxes for individual pipe cuts has been eliminated. These devices require considerable time and exposure to install and remove, and during the Unit 2 SGRP were found in many cases to be counter-productive to ALARA due to this fact.

(b) The use of temporary containments, -especially as applied to the lower steam generator cubicles, has largely eliminated delays and interference with work being performed in adjacent areas while cutting and grinding of contaminated piping is in progress.

(c) The overall potential for airborne contamination and problems associated with contamination control have been minimized by effective use of temporary containments and portable ventila-tion.

3.6 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 have been implemented to assure adequate control of occupational radiation exposure and to maintain this exposure ALARA. These include:

(a) A comprehensive health physics program to provide adequate control and surveillance of the radiation hazards associated with each task. This program includes the use of Radiation Work Permits (RWP' s) with an individual "sign-in" system to ensure

  • worker familiarization with the specific radiological hazards involved and proper protective measures to be taken in the performance of their work.

(b) A training program to provide adequate 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 mock-ups, photographs, or "dry runs" is conducted where appropriate. Additionally, the video-tape documentation compiled during the Unit No. 2 SGRP is being

  • e PR3-9 SSGP utilized to provide all personnel with a general understanding of the repair program. In this way*, each worker is more fami-liar with the sequence of events to take place and the manner in which individual tasks relate to the overall repair effort.

(c) The use of discrete "Work Packages" to assure adequate pre-planning and review . of specific tasks, with special emphasis placed on minimizing the radiation exposure to personnel

  • involved.

(d) The establishment of "rest areas" to accommodate workers during idle periods. Rest areas within the containment are located where exposure rates are low (2-3 mR/hour on the average). Additionally, for the Unit 1 replacement a "rest trailer" has been located outside the containment equipment hatch on the operating deck level where radiation levels are typically 0.1 mR/hour. These rest areas are well posted for identification and workers are encouraged to utilize these areas whenever possible to avoid unnecessary exposure.

Although quantitative assessments are not possible for these "general" techniques, all have obvious value in contributing to the overall ALARA program for the steam generator replacement project.

4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE PR3-10 SSGP 4.1 General Radioactive liquid and gaseous effluents, and radioactively conta-minated solid wastes generated during the SGRP for Unit No. 1 are attributable to several sources. In general, these sources can be distinguished w:tth reasonably accuracy from those associated with concurrent operation of Unit No. 2, even though shared processing systems are utilized in some cases.

4.2 Airborne Releases Airborne releases during the reporting period originated primarily from the continuous ventilation of the containment during the repair effort, to maintain a negative pressure while the equipment hatch .is open. This continuous ventilation is processed through appropriate filter banks to minimize the concentration of airborne particulates which may result from activities inside the contain-ment.

4.3 Liquid Releases The major contributor to liquid releases during this reporting period continues to be disposal of laundry waste water. Laundry wastes are expected to comprise the predominant source of liquid releases during the remainder of the repair effort, as was observed during the SGRP for Unit No. 2.

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 continued to comprise the major portion of the solid radioactive waste generated during the reporting period.

The quantities of radioactive materials released in liquid and gaseous effluents, and the amounts of solid radioactive waste shipped offsite for disposal during this reporting period are summarized in Table 2.

PAGE 1 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 1/1/81 - 2/28/81 SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS PHASE LABOR TO-DATE EXPOSURE PERIOD DESCRIPTION TO-DATE (CaCOMPLETE)

(MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM)

~

(MAN-REM) (I*IN PROGRESS)

      • COMPLETED TASKS ONLY***

I Shutdown and Preparatory 35,371 46,763 326.22 1.688 Activities 147.576 C II Removal Activities 57,422 165,708 559.6 18.167 450.629 C III Installation Activities 0 0 0 0 0 I IV Post Installation and 898 138 4.49 0.023 Startup Activities 0.093 I V Steam Generator Storage 300 937 35 0 Activities 8.079 C PROJECT TOTALS 93,991 213,546 925.31 19.878 606.377 (Completed Tasks Only)

PAGE 2 of 14 TABLE* 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 1/1/81 - 2/28/81 SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE PHASE PHASE DESCRIPTION ESTIMATED LABOR (MANHOURS)

EXPENDED TO-DATE (MANHOURS)

ESTIMATED EXPOSURE (MAN-REM)

FOR REPORTING PERIOD (MAN-REM)

EXPENDED TO-DATE (MAN-REM~

STATUS (C=COMPLETE)

(I*IN PROGRESS) e,

      • ALL TASKS COMMENCED AS OF 2-28-81***

I Shutdown and Preparatory 39,021 48,829 596.27 4.464 207.861 C Activities II Removal Activities 57,422 165,708 559.6 18.167 450.629 C III Installation Activities 74,195 182,817 448.23 183.974 313.190 I IV Post Installation and 62,650 47,289 427.54 61. 772 80.837 I Startup Activities V Steam Generator Storage 300 937 35 0 8.079 C Activities PROJECT TOTALS (All Tasks) 233,588 445,580 2,066.64 268.377 1,060.596 e.

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PAGE 3 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

Erect Equipment Hatch 264 0 0.4 0 0 C Temporary Enclosure Prepare and Load Test 210 463 1.05 0 1.285 C Polar Crane Open Equipment Hatch 156 0.23 C (See Note 1)

Defueling and Fuel Storage 585 2,863 11. 7 0 23.503 C Install Reactor Vessel 130 695 1.3 0 1.813 C Cavity Cover Cutting of Pressurizer (See Note 2)

Cubicle Wall Installation of Jib Cranes 1,838 3,348 9.19 0.010 5.256 C Disassemble Manipulator Crane 58 629 1. 74 0 1.533 C Install Steam Generator 572 3,947 2.86 0.508 6.950 C Transport System Removal of Biological 1,296 916 19.44 0 2.298 C Shield Wall

PAGE 4 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM} ~I-IN PROGRESS)

Disassemble Shroud Cooling 150 601 3 0 1.228 c-System Cutting of Crane Wall at 432 548 2.16 0.333 1.156 C Hatch Opening Installation of Temporary 50 106 0.05 0 0.053 I Ventilation System Temporary Scaffolding 7,500 4,846 75 0.535 14.786 C Temporary Lighting 5,200 2,174 26.25 0.028 2.162 C and Power Cleanup and Decon 9,000 14,920 135 0 57.975 C Polar Crane Operator 1,500 198 4.5 0 0.137 C Shielding 3,600 1,960 270 2.776 60.232 I H.P., Q.A. 6,480 6,884 32.4 0 9.956 C ADDITIONAL TASKS Installation of Service 627 0 2.198 C Air System

PAGE 5 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I - SHUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C,.COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

Work Platform Modification 1,816 0 0.741 C Protection of Containment 1,288 0.022 6.128 N/A Components UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 0.252 8.471 N/A and Administration Subtotal Phase I 35,371 46,763 326.22 1.688 147.576 (Completed Tasks Only)

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PAGE 6 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (CaCOMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) ~I-IN PROGRESS)

Removal of Insulation 720 1,647 28.8 0 14.000 C (lower shell, RC piping)

Removal of Insulation (upper shell, 864 959 12.96 0 5.354 C mainsteam and feedwater piping)

Removal of Miscellaneous 72 1,288 1.8 0 13.896 C Piping Set Up Steam Generator 1,152 90 28.8 0 0.208 C Girth Cut Equipment Cut and Remove Steam 330 5,529 8.25 1.033 9.173 C Generator Upper Shell Cutting of Reactor 2,982 7,181 149.l 0 76.682 ~

Coolant Piping Cutting of Mainsteam and Feedwater Piping 1,428 1,399 7.14 0 2.391 C e

Disassembly of Steam 792 6,988 15.84 1.053 55.120 C Generator Supports Removal of Moisture 396 5,321 1.98 1.487 9.402 C Separation Equipment Refurbish Steam Generator 9,246 11,458 46.23 3.797 9.887 C Upper Shell

PAGE 7 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE) '~

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM~ ~I*IN PROGRESS)

Removal of Steam Generator Level 135 1,472 4.05 0 6.389 C Instruments and Blowdown Piping Removal of Steam Generator 1,575 4,326 31.5 0.001 22.738 C Lower Shell Temporary Scaffolding 7,500 13,611 75 2.942 40.919 C Temporary Lighting 5,250 5,356 26.25 0.152 4.451 C and Power Cleanup and Decon 17,000 44,732 85 3.315 88.604 C Polar Crane Operator 1,500 2,365 4.5 0.061 2.428 C .

H.P., Q.A. 6,480 27,502 32.4 1.598 33.740 C e:

ADDITIONAL TASKS Material Handling, Equipment 24,484 1.342 35.868 N/A Maintenance, and Miscellaneous Construction Activities

PAGE 8 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION - UNIT NO, 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (CaCQMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS} (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS)

UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 1.386 19,379 N/A and Administration Subtotal Phase II 57,422 165,708 559.6 18.167 450.629 (Completed Tasks Only)

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PAGE 9 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

I PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 TASK DESCRIPTION Steam Generator Lower Shell Installation ESTIMATED LABOR (MANHOURS) 1,926 ACTUAL LABOR EXPENDED TO-DATE (MANHOURS) 8,133 ESTIMATED EXPOSURE

{MAN-REM) 9.63 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM) 2.231 ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM) 16.885 TASK STATUS (C*COMPLETE)

{I*IN PROGRESS)

I Installation of Reactor 6,768 14,134 67.68 36,386 70.652 I Coolant Piping Steam Generator 5,400 12,941 27 3.455 9.159 I Girth Weld Installation of 3,735 5,126 18.68 1.093 2.356 I Main Steam Piping Installation of 2,700 4,193 13.5 1.335 1.519 I Feedwater Piping Installation of Blowdown and 1,782 4,675 17.82 15.641 15.641 I e

Miscellaneous Piping Install Steam Generator 2,592 6,104 12.96 7.820 7.820 I Level Instruments Installation of 11,562 155 57.81 0.293 0.293 I Insulation Temporary Scaffolding 7,500 11,059 75 17.921 29.784 I Temporary Lighting 5,250 2,857 26.25 0.926 2.009 I

& Power

PAGE 10 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE III - INSTALLATION ACTIVITIES SURRY POWER STATION - UNIT NO. 1 TASK DESCRIPTION ESTIMATED LABOR (MANHOURS)

ACTUAL LABOR EXPENDED TO-DATE (MANHOURS)

ESTIMATED EXPOSURE (MAN-REM)

ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM)

ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM)

TASK STATUS (C*COMPLETE)

{I*IN PROGRESS) e Cleanup and Decon 17,000 51,101 85 46.411 79.283 I Polar Crane Operator 1,500 3,593 4.5 0.860 1.874 I H.P., Q.A. 6,480 31,116 32.4 22.370 31.879 I ADDITIONAL TASKS Material Handling, Equip- 27,630 18.792 30.708 N/A ment Maintenance, and Miscellaneous Construction Activities UNASSIGNED PERSONNEL CATEGORIES Project Supervision Not Reported 8.440 13.328 N/A and Administration Subtotal Phase III 0 0 0 0 0 (Completed Tasks Only)

PAGE 11 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (CmCQMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM~ ~I.,IN PROGRESS)

Install Biological 3,240 598 16.2 0.847 0.918 I Shield Wall Repair Crane Wall 473 91 2.37 0.009 0.079 C Opening Repair Pressurizer Cubicle (See Note 2)

Wall Install Steam Generator 9,000 ll, 190 90 17.316 31.399 I Recirculation and Transfer System Remove Reactor Cavity 130 0 0.65 0 0 I Cover Install Reactor Cavity 240 0 1.2 0 0 I Coaming Reassemble Manipulator 1,176 127 23.25 0 0.346 I Crane Remove Steam Generator 425 47 2.12 0.014 0.014 C Transport System Reassemble Shroud 576 2,379 11.52 1.978 2.908 I Cooling System Hydrostatic Tests 75 55 0.38 0.060 0,060 I

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PAGE 12 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 TASK ESTIMATED LABOR ACTUAL LABOR EXPENDED TO-DATE ESTIMATED EXPOSURE ACTUAL EXPOSURE FOR REPORTING PERIOD ACTUAL EXPOSURE EXPENDED TO-DATE TASK STATUS (C*COMPLETE) e*

DESCRIPTION (MANHOURS) {MANHOURS) (MAN-REM) {MAN-REM) {MAN-REM) ~I*IN PROGRESS)

Refueling 585 0 11. 7 0 0 I Temporary Scaffolding 7,500 2,915 75 5.350 7. 722 I Temporary Lighting 5,250 705 26.25 0.276 0.492 I and Power Cleanup and Decon 17,000 12,578 85 16.575 16.575 I Polar Crane Operator 1,500 951 4.5 0.308 0.308 I Painting 9,000 268 45 1.818 1.818 I H.P., Q.A. 6,480 8,209 32.4 7.989 7.989 I ADDITIONAL TASKS Material Handling, Equipment 7,176 6. 712 6. 712 N/A Maintenance, and Miscellaneous Construction Activities

i' PAGE 13 of 14 TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION - UNIT NO. 1 TASK DESCRIPTION UNASSIGNED PERSONNEL CATEGORIES ESTIMATED LABOR (MANHOURS)

ACTUAL LABOR EXPENDED TO-DATE (MANHOURS)

ESTIMATED EXPOSURE (MAN-REM)

ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM)

ACTUAL EXPOSURE EXPENDED TO-DATE (MAN-REM)

TASK STATUS

( C*COMPLETE)

(I*IN PROGRESS) -

-Project Supervision Not Reported 2.520 3.497 N/A and Administration Subtotal Phase IV 898 138 4.49 0.023 0.093 (Completed Tasks Only) e

ri I

PAGE 14 of 14 [

TABLE 1 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE V - STEAM GENERATOR STORAGE ACTIVITIES "

SURRY POWER STATION - .UNIT NO, 1 i ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO-DATE EXPOSURE PERIOD TO-DATE (C*COMPLETE)

DESCRIPTION (MANHOURS) (MANHOURS) (MAN-REM) (MAN-REM) (MAN-REM) (I*IN PROGRESS) l Steam Generator Storage 300 937 35 0 8.079 C Activities

          • a*********~***********************************=************a*a*=****~m********m~***~******************************************************  ;.

TABLE NOTATION i

1.

r

1. 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.

2. This task was cancelled due to equipment changes. Labor and Exposure Estimates are not included in the Subtotal Values.

N/A - Not Applicable. Labor and Exposure Expenditures are included in the Subtotal Values for Phases I and II. They are not included in the Subtotal Values for Phases III.and IV (See Report Section 2.3.c).

e

  • TABLE 2 SURRY POWER STATION PAGE 1 , of *6 STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1980 I

September I October Novemhe~ T\~---'-,p,-

  • I=~'

UNl:TS I, LIQUID RELEASES Curies Isotooe: Released MPC uci/ml 3 X 10-1 I-131 5.96E 5 t, a ~"-'i  ? """-1

  • 1-132 8 X 10-6 1-133 1 X 10-6 1 73E-6 1.32E 5 3.47E-7 I-134 2 X 10-"

I-135 4 X 10-" *

  • Cs-134 9 X 10 .b 3.0lE-4 8.32E-4 2.48E-2 'L..c,o.e.-4 Cs-137 2 X 10-* l.04E-3 2.38E-3 3.35E-2 8.0BE-4 Co-57 4 X 10-" 1.89E-6 3.57E-7 Co.-5H 9' X 10 .,

5.73E-4 1 n,,,_1 1.36E-2  !:l,bOE-4 Co-f>O 3 X 10-* 1. lOE-3 'i.72F-1 1.BlE-2 3.48E-3 Mn-54 1 X 10-* 3.36E-5 1 llE-4 2.78E-3 4.45E-5 Na-24 3 X 10 ., 1.17E 3 6.29E-3 '*""

Cr-51 2 X 10-3

  • 1.14E-4 1.99E-4 4.87E-4
  • Fe-59 !i X lQ-5 Nb-95 1 Y , n_" 1. llE-5 S.68E-5 3.66E-5 21F.. c; Sb-124  ? V ,n_,
  • 1.20E-6 -* -

Sb-125 1 V 1n- 4

  • 3.86E-5 7.SOE-7 1.44E-6 Zn-b.5 1 x , n. 4 2.60E-6 Zr-95 , * *
  • Mo-99 6 X 10-4 X 10- 5 Ru-103 8 X 10- 5
  • 1.89E-6 * '*

Xe-133 3 X 10- b 8.66E-5 4.74E-4 1.BSE-2 3.68E-6 Xe-135 Xe-133m 3 X 10-"

3 X 10- 6 *

  • 7.48E-5 1.lSE-5 2.41E-3 Ar-41 3 X 10- 6
  • 8.38E-7 *
  • Ag-llUm 1i' Nf-O.j 3 X 10-"

3 X 10-5 * *

.1.JSF.-3 1:ooE-J 4.0lE-5 1.41E-3 Fe-55 8 X 10- 0 1.16E 4 1.12E 2 *"'

Ce-144 1 X 10- 6

  • 3 X 10- 3
1. 77E-7 Tc-99m * *
  • Ce-141 9 X 10- 0
  • 9.0BE-7 * "'

Volume of Liquid to Discharge Canal T ~t-p,-Q 6.70E+4 5.89E+S 1.16E+6 4.76E+5

  • Not Detected
    • Sample analysis results not yet received from service vendor.

Upon receipt, analysis data will be included in subsequent

  • nro~resa rP.oorte,

TABLE 2 SURRY POWER STATION PAGE 2 of~6~-

STEAM GEN°~Rl\TOR REPJ,ACEMF.N'l' PROJECT REPORT OF RADIOACTIVE i~rf.Ltfif~ YEAR: 1980

- *- &. --~=--~--:-J * .. .::.. - -- - -

' I II. AIRBORNE RELEASES Ii~ - --- - - - - -~"':'I'- k ---- "2*-= - ..

-UNITS September October November !December I

-- *\1

~- - .1.- - -- ~--~- ..-~ "'"='='= *--.-- ---= .- - .. - **- -- - . ----- . --- . ...

,~*Isotopes Released: Curies (a) Particulates Cs-134 3.12E-6 1 22E-6 2.73E-6 Cs-137 -

9.07E-6 1. 76E-5 8.66E-5

  • 2.21E-5 Cr-51 4.42E-5 Co-58 2.63E-5 1.65E-5 5.02E-5 1.65E-5 l.94E-5 Co-60 3.49E-5 c;. Q'iF.-~ 5.97E-5 6.27E-5 Mn.:.54 * *
  • I Fe-59 *
  • Cs-138 1.0lE-4 * "

Rb-88

  • c; ?l.F.-'i *

,b) Halogens I-l,31 l.78E-3 fi 15F.-L. 7.90E-4 l.74E-5 '

- I-132 4.73E-6 1.31E-6

  • I I-;!,33 2.12E-6 2.31E-5 4.03E-5 T-1 'll..

'I T-11<;

(r) Gases Xe-133 4.44E+2 5.26E+l

  • 5.22EO Xe-133m 7.89EO Xe-135 Kr-85m 3.21E-1 Kr-85 * * "
  • Kr-87 * * *
  • Kr-88 * * "
  • Ar-41 * * " "

Xe-131m S.45E+2 " "'

H-3 7 .OBE-1 2,lSE-1* 6.97E-2 S.62E-2 ...

1-

,I

    • - ~
  • Not Detected
  • - - - . *-. ***~.

--- ~----

~ *-- - - * -* ...... - - --=-r ===- T:- - e - , " ' : : " : : " " ~ - = - ~ . . . . . . . . - = ~ .~ ~-- .. *-

-1 "T"_,.

~

\i TABLE 2 SURRY POHER STATION PAGE~-3~of----'6'--~

STEAM GENERATOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1980 nr. SOLID RADIOAeTIVE WASTE DISPOSAL ,. ----. - -

I Units lc:o~t-.omh~r- - nPrPm~=I~

Isotopes Released: Curies - I (a) Total Amount of Solid Waste Packa!!ed . FT 3 0 3.94E+3

  • 6.30E+3 1.64E+4

' f (b) Estimated Total Activity Curies -0 1 45F.+O 1.82E+l 8.54E+O (c) Date of Shipment and Disoosition

!11 to s:gwell,

!11 to arnwell, !F arnwe ton

. _o **- ~ (' ~ ('

10 15-80 11-3-110 12-1-80 2)

- -* 10 21 80 11 4-80 12-2-80 2) 10-23-80 11 6 80 12-3-80 2)

- *- 10-28-80 11-7-80 (2) 12-4-80 , 2)

. 10 30 80 11 10-80 12-5-80 (2) 11 12-80 12.-8-80 f

11-11-80 12-11...:80<2)

.. 11 14-80 12-I2-80

-- 11-18-80(2) 12-15-80

. 11-19 80 12-16-8.0 12-17-80 12-18-80 12-19 80 12-22-80, 12-30-80 <2)

~~--1

-*- - . -- - - - - =-- ..*

'~Not Detected

\

~ I

l TABLE 2 SURRY POWER STATION PAGE_4_of_6_

. ,REPORT OF RADIOACTIVE EFFLUENTS YEAR: 1981

'JANUARY FEBRUARY '

UNtTS I. LIQUID RBLBASBS Curies Isotnne: Released HPC uCi/ml 1-131 3 X 10-'1 1,32E-6 1-132 8 X 10-6 1-133 1 X 10- 6 1-134 2 X 10-b 1-135 4 X 10-5 *

  • Gs-134 9 X IO-"

4.0lE-4 6.00E-4 Cs-137 2 X IO-" 1.49E-3 l.60E-3 Go-57 4 X 10-~ 8.28E-7 l.27E-5 Co,-:,11 V x 10-" l.69E-3 6;5QE-4 Co-60 3 X 10-~ 7.64E-3 4,30E-3 Mn-54 .1 X 10-~ l.BlE-4

  • 5.00E-5
  • Na-24 3 X 10-~ 2.00E-4 Cr-51 2 X 10-* 2.21E-5 Fe-59  ;; ,. 1n-"

Nb-95 1 ,. ,n_" 3,07E-5 4.BOE-6 Sb-124 , ... 1n_b '

Sb-12:, 1 .,. 10-" i.13E-6*

  • 2.30E-4 Zn-65 1.25E-6 Zr-Y:>

1 x 1n-"

  • Mo-99 Ii ,r 10-D 4 x 10- 5 .". .."

Ru-103 Xe-133 8 X 10-11 3 X 10-* i:;. 01 .. _,; 1 nn1>_'l.

Xe-135 3 X 10-* 1 nnR-6.

  • Xe-133111 3 X 10- 5
  • 1 nn"-"

Ar*41 3 X 10-'"

  • Ag-lJ.Um ] X 10-" *
  • ':,Ir *
  • .'*,Ir Ni-11-' ] X 10- 11 Fe-55 8 X 10-D ** **

Ge-144 . I. X 10-"

1.31E-5 **

Tc-99m J X 10-* "

Ce-141 !IX 10-"

Volume of Llauid to D1scbarse Gsnal ,,_.... _.ft 7,40E+5 8,00E+5

  • Hot Det~ted
    • Smnple analysis results not yet received frDIII service vendor, Upon receipt, analysis data will be included in s.ubsequent progress reports,

\

TABLE 2 SURRY POWER STATION PAGE S* of 6 STEAM GENERnTOR REPLACEMENT PROJECT REPORT OF RADIOACTIVE EFFLUENT~ YEAR: 1981 JANUARY FEBRUARY II, AIRBORNE RELEASES "UNITS Isotopes Released: Curies (a) Particulates

-J Cs-134 l.69E-5 Cs-137 l.lSE-4 7.13E-6 Cr-51 Co-58

  • 2.82E-4 Co-60 5.44E-4 l.24E-4 Mn-'.>4 l.92E-5 Fe-;-59
  • l;S-.l,jt!

Rb-88 (b) Halogens 1-131 2.15E. 6 1-132 I-133 *

  • 1-134 * *

., 1-135 * *

(c) Gases Xe-133

  • Xe-133m I

Xe-135 * *ft

- Kr-8Sm

  • Kr-87 *
  • Kr-88 *
  • Ar-41 *ft
  • Xe-131m
5.BOE-2 *

.J.33E-2

  • Not Detected
  • -\I r"

m.l,~

SURRY'POWER STATION STEAM GENERATOR REPLACEMENT PROJECT PAGE ~ 6 - of - 6 REPORT OF RADIOACTIVE EFFLUENTS YEAR:_!1.981 JANUARY FEBRUARY III. SOLID RADIOACTIVE WASTE DISPOSAL Units Isotones Released: ,Curies

- - ---- -- --****- " - - - * - -Ho -* ---

(a) Total Amount of Solid Waste

--~ '----*--- I I I I Packa2ed FT 3 7 .48E+3 9.33E+2*

(b) Estimated Total Activity curies 6.32E+o 1.01E+4 (c) Date of Shipment and Barnwell, Barnwell, Disnosition s.c. s.c. ':

1-f',-Rl  ?-'1-Rl 1-R-Rl  ? _/,-Al 1_Q .Al 7_i;_A1

'-1'1-A1  ? -'--111 1_1,._111 , .,n_a, 1-l'i-Rl  ?-1 ?-Al 1_?0-Rl ?_1'1-111 1-?1-111  ?-1 r.-Al 1-'>"-Rl 7-1A-A1

~-?n _11,

,_.,n_a,

  • -**-* -* -*---*-*- - --* .. .. *---*-----
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