ML18136A367

Steam Generator Repair Program,Progress Rept 5 for Oct-Nov 1979

ML18136A367
Person / Time
Site:	Surry
Issue date:	11/30/1979
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18136A366	List: ML18136A365 ML18136A367
References
NUDOCS 8001100494
Download: ML18136A367 (29)

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STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NO. 2 PROGRESS REPORT - NO. 5 FOR THE PERIOD OCTOBER 1, 1979 THROUGH NOVEMBER 30, 1979 DOCKET NOS. 50-280 50-281 LICENSE NOS. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY I

r 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 Miscellaneous Valve Refurbishment 3.4 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.

PR5-l PR5-2 PR5-2 PR5-2 PRS-3 PRS-4 PRS-5 PRS-5 PRS-5 PR5-6 PR5-6 PRS-7 PRS-7 PRS-7 PRS-7 PRS-8 PR5-9

1.0 INTRODUCTION

PRS-1 SSGP 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 October 1 through November 30, 1979.

With regard to radiological effects, significant tasks performed during the reporting period involved installation and post-instal-lation and startup activities and included: installation of removed reactor coolant pipe sections, installation of blowdown and miscel-laneous piping and installation of the steam generator recirculation and transfer system.

Several ongoing peripheral and support activi-ties such as temporary scaffolding, cleanup and decontamination, heal th physics support and project supervision 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 effectiveness, and the radioactive effluents and solid waste generated during the reporting period.

2.0 OCCUPATIONAL RADIATION EXPOSURES 2.1 General PRS-2 SSGP Occupational exposure to radiation may be considered the major radiological effect of the SGRP.

Thus, significant importance has been placed upon providing an accurate assessment of the collective radiation exposure 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 established 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 estimated and actual exposures for specific tasks.

In general, the program utilizes daily worker exposure data, as recorded by self-reading pocket dosimeters, 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

PRS-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 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 February 3, 1979 to November 30, 1979), and the original estimated expenditures.

The following commen.ts 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 included in Table 1.

Similarily, 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 o~ 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.

PRS-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), Phase II (Removal Activities), and Phase III (Installation Activi-ties).

For Phase IV (Post Installation and Startup Activities) the Phase Subtotals do not yet include the expenditures men-tioned above since a majority of the tasks involved in this phase have yet to be completed.

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 November 30, 1979 is approximately 4% below the original estimate.

Furthermore, no worker assigned to the SGRP has to date received radiation exposure in excess of applicable federal standards.

These facts, 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.

I ___ _

3.0 APPLICATION OF ALARA PRINCIPLES 3.1 General PRS-5 SSGP This section summarizes the techniques and practices which have been effective. in providing dose reductions to personnel during the reporting period.

Where the available data.permits, the following evaluations include a quantitative assessment of the manrem savings which can be attributed to the technique used.

Additional infonna-tion on these techniques and how they relate to the overall steam generator replacement activities can be found in the SGRP report.

3.2 Temporary Shielding The use of temporary shielding, and the significant exposure rate reductions achieved through its application, have been described in detail in several previous Progress Reports for the SGRP.

The lower steam generator cuhicles have received the most extensive application of shielding and thus the work performed in these areas has benefitted most directly from its use.

During the re-porting period, a number of tasks involved some degree of work in the lower cubicles, however, the installation of reactor coolant piping represents the most significant manrem expenditure for which the effectiveness of shielding can be assessed.

Using radiation survey data, it was shown in Progress Report Nos. 3 and* 4 that an average exposure rate reduction* factor of 5 was achieved through temporary shielding of reactor coolant piping.

By applying this reduction factor to the actual exposure expended for installation of reactor coolant piping during the reporting period (approximately 19 manrem) a calculated exposure savings of about 76 manrem is obtained.

i I __

3.3 Miscellaneous Valve Refurbishment PRS-6 SSGP In section 3. 3 of Progress Report No. 4 for the SGRP, the re fur-bishment of valves removed from miscellaneous piping syst~ms.* was--- ---

I discuss.ed.

It was shown that significant reductions in radiation~.. -.

exposure levels associated with the valves resulted from this re-furbishment and that a dose reduction factor of 10 could be assign-ed to subsequent tasks requiring handling of the valves.

During the reporting period, "Installation of Blowdown and Miscel-laneous Piping" required the expenditure of*approximately 32 manrem.

Of this total, installation of miscellaneous piping (and valves),,"

represents about 20 manrem.

The achieved dose reduction factor of 10 can thus be used to calculate an exposure savings of about 180 manrem for this sub-task.

3.4 General Techniques A number of more general techniques and practices are listed below which have been utilized throughout the repair effort to maintain adequate control of occupational radiation exposure.

(a)

Comprehensive Health Physics and training programs, (b) the "work package" concept for task preplanning and review, (c) the project photographic and video-tape documentation, (d) in-containment "rest area" uti_lization, and (e) periodic work area cleanup and debris removal.

While these practices cannot be related quantitatively to any speci-fie task, they all contribute significantly to the overall Al.ARA program for the SGRP.

4.0 RADIOACTIVE EFFLUENTS AND SOLID WASTE 4.1 General PRS-7 SSGP 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 envi~onment. Releases for October and November are seen in Table 2 to be consistent with those of the previous six 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 effluents released during the reporting period is relatively unchanged from that seen during the previous period.

The major contributing nuclides are present at quantities which have remained consistent throughout the project.

It should be noted that the concurrent outage for Surry Unit No. 1 during October (as during previous months) may have contributed to the quantities of radioactive liquids released to the. discharge

PRS-8 SSGP canal; 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 wa.ste, 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.

5.0 *CONCLUSIONS PRS-9 SSGP The following general conclusions are based upon the information

.. contained within this report.

(a)

Although some variations can be seen when co~paring the esti-mated vs. actual exposu~e expenditures for individual tasks, the total exposure (manrem) expended to date remains below the original estimate establishe~ 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 effectively implemented and applied to the steam generator replacement activities.

b)

Radioactive liquid effluents have exceeded the total release estimate for activity presented on page 9.A.5-5 of the SGRP report by approximately 38%.

The total volume released to date, however, is only 16% higher than the estimated total.

This. indi-cates that liquid effluent concentrations are somewhat higher than originally anticipated. It has also been noted that some contributions to the liquid releases reported have occurred due to the concurrent outage for Unit No. 1.

Nevertheless, the total activity released to date continues to represent 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 estimates during the remainder of the project.

(d)

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 has been previously attributed

PRS-10 SSGP to the increase in personnel assigned to the SGRP, and the ex-pected subsequent generation of higher volumes of contaminated paper waste, disposable protective clothing and contamination control materials. It should be noted, however, that a signi-ficant reduction in both the volume and activity of solid waste shipped during the months of September, October and November occurred.

This reflects the reduced level of work being performed as the SGRP for Unit No. 2 nears completion.

I*

ESTIMATED PllASE LABOR Ii DESCRIPTION (MANllOUllS)

I Shutdown and Preparatory Activitiea 39!021 II Removal Activities 57,422 Ill Installation Activities 51,491 IV Post Installation and Startup Activities 3,020 v

Steam Generator Storage Activities 300 PROJECT TOTALS (Completed Tasks Only) 151,254

.e TABU l PAGE 1

OF 13 PERSONNEL RADIATION EXPOSUllE

SUMMARY

STEAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 10/ l/79-11/30/79 SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR EXPENDED ESTIMATED TO - DATE EXPOSURE (MANUOURS)

(MAN-LI.EM)

• • • COMPLE'l'EO TASKS 152,731 596.27 190,601 559.6 288,067 291.96 5,730 41.11 3,659 35.0 640, 788 l,5JJ.94 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM)

ONLY***

0.195 1.341 55.838 4.623 0.174 62.171 ACTUAL EXPOSURE EXPENDED TO - DATE (MAN-REM) 387.523 699.641 362.247 5.896 5.054 l,460.361 PHASE STATUS (C=CONPLETE)

(I=IN PROGRESS) c c

I I

c

ESTIMATED PHASE LABOR DESCRIPTION

~MANllOURS)

I Shutdown and Prepara,-

tory Activities 39,021 II Removal Activities 57,422 III Installation Activities 7",195 IV Post Installation and Startup Activities 62,065 v

Steaiu Generator Storage Activ-Hies 300 PUOJECT TOTALS (All Tasks) 233,003 TABLE l PERSONNEL RADIATION EXPOSURE SUMMAUY PAGE -.2-OF __ll_

Sl'EAM GENERATOR REPLACEMENT ACTIVITIES - REPORT PERIOD 10/ l/79-ll/30/79 SURUY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAi. EXPOSURE EXPENDED ES1'1MATED FOR REPORTING EXPENDED

'I'D -

DATE EXPOSURE PERIOD TO - DATE

~MANllOURS)

~MAN-REM}

~MAN-REM}

(MAN-REM)

• • • ALL TASKS COMMENCED AS OV 11/30/79***

152,731 596.27 0.195 387.523 190,601 559.6

1. 3"1 699.6"1 417,261 448.23 124. 222 794.172 71,255 415.84 38.258 ll0.519 3,659 35.0 0.174 5.054 835,507 2;05t1.94

• 164.1.90 1,996.909 PUASE STATUS (C=COMPLE'l'E)

(I=IN PUOGRESS}

c c

I I

c

TABLE l PAGE 3

OF 13 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I-SHUTDOWN AND PREPARATORY ACTIVl'l'IES SURRY PO\\.IER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ES'l'IMATED

~'OR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO -

DATE (C=COMPLETE)

DESCRIPTION

~MANllOURS)

~MANUOUltS}

~MAN-REM)

(MAN-REM)

~MAN-REM)

~I=IN PROGRESS)

Erect Equipment Hatch Temporary Enclosure 264 1,073 0.4 0

0.459 c

Prepare and Load Test Polar Crane 210 2,757 l.05 0

2.883 c

Open Equipment Hatch 156 0.23 c

(See Note 1)

Defueling and Fuel Storage 585 3,437 l l. 7 0

22.124 c

Install Reactor Vessel Cavity Cover 130 2,385 1.3 0

1.972 c

Cutting of Pressurizer (See Note 2)

Cubicle Wall Installation of Jib Cranes 1,838 13,2311 9.19 0.020

14. 713 c

Disassemble Manipulator Crane 58 1,501

l. 74 0

2.416 c

Install Steam Generator "l'ranspor~ System 572 7,451 2.86 0.138 12.820 c

Removal of Biological Shield Wall 1,296 3,959 19.44 0

3.392 c

Disassemble Shroud Cooling System 150 918 3.0 0

1.520 c

,-e TABLE l PAGE __!J_ O~' JL PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I-SHUTDOWN AND PREPARATORY AC'l'IVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPOR1'ING EXPENDED STATUS TASK LABOR TO - llATE EXPOSURE PERIOD TO - DATE (C;COMPLE'l'E)

DESCRIPTION

~MANllOURS}

~HANllOURS}

~MAN-REM}

(MAN-REH)

(MAN-REM)

(I;IN PROGRESS)

Cutting of Crane Wall at llatch Opening 432 1,379 2.16 0

0.446 c

Installation of Temporary Ventilation System 50 11,455 0.05 0.026 4.210 c

Temporary Scaffolding 7,500 14,559 75 0

74.363 c

• remporary Lighting and Power 5,200 6,609 26.25 0

0.563 c

Cleanup and Dec on 9,ooo 17,216 135 0

22.601 c

Polar Crane Operator 1,500 1,368 4.5 0

2.319 c

Shielding 3,600 21,930 270 0

143.493 c

H.P., Q.A.

6,480 31,286 32.4 0

33.584 c

ADDITIONAL TASKS Installation of Service Air System 2,491 0

0.670 c

Work Pl{ltform Modification 5,272 0.011 0.181 c

Removal of Reactor Coolant Pump Motors 1,357 0

4.621 c

19 TASK DESCRIPTION Protection of Contain-ment Components ESTIMAl'ED LABOR (MANHOURS)

UNASSIGNED PERSONNEL CATEGORIES Engineering Support Craft Support and Security Escorts Project Supervision and Administration Visitors and Inspectors Subtotal Phase I (Completed Tasks Only) 39,021 TABLE l PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE I-SllUTDOWN AND PREPARATORY ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR EXl'ENDED TO - DATE (MANHOURS) 1,094 Not Reported 152,731 ESTIMATED EXPOSURE (MAN-llEM) 596.27 ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM) 0 0

0 0

0 0.195 PAGE _5_ OF 13 ACTUAL EXPOSURE TASK EXPENDED STATUS TO - DATE (C;COMPLETE)

(MAN-REM)

(I;IN PROGRESS) 4.054 N/A 5.657 N/A 10.000 N/A 17.227 N/A 1.235 N/A 387.523

TABLE l PAGE 6 OF 13 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION-UNIT NO. 2 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

{MANllOURS}

{MANllOURS}

(MAN-REM}

(MAN-REM)

(MAN-REM}

~I-IN PROGRESS}

Removal of Insulation (lower shell, RC Piping) 720 2,026 26.8 0

13.791 c

Removal of Insulation (upper shell, mainsteam and radwater piping) 864 80 12.96 0

l.36lt c

Removal of Miscellaneous Piping 72 5,lt24 l.8 0

59.337 c

Set Up Steam Generator Girth Cut Equipment 1,152 22lt 28.8 0

0.229 c

Cut and Remove Steam Generator Upper Shell 330 5,079 8.25 0

11. 22 l c

Cutting of Reactor Coolant Piping 2,982 20,235 149.l 0

2llt.058 c

Cutting of Hainsteam and Feedwater Piping 1,428 2,838 7.14 0

1.132 c

Disassembly of Steam Generator Supports 792 10,650 15.8lt l.3ltl L,8.412 c

Removal of Moisture Separation Equipment 396 6,050 l.98 0

6. 727 c

Refurbish Steam Generator Upper Shell 9,2lt6 21,756 L,6.23 0

19.619 c

II TABLE l PAGE 7

OF 13 PERSONNEL RADIATION EXPOSURE SilllMARY PHASE II - REMOVAL ACTIVITIES 1:

SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=COMPLE'l'E)

DESCRIPTION

~MANHOURS}

~MANllOURS)

(MAN-REM)

~MAN-REM)

(MAN-REM)

~ I=IN PROGRESS)

Removal of Steam Generator Level Instrwnents and Blow-down Piping 135 2,311 4.05 0

7.671 c

Removal of Steam Generator Lower Shell 1~575 3,859 31.5 0

29.875 c

Temporary Scaffolding 7,500 11, 969 75.0 0

46. 464 c

Temporary Lighting and Power 5,250 6,071 26.25 0

5.910 c

Cleanup and Dec on 17,000 26, 731 85.0 0

83. 718 c

Polsr Crane Operator 1,500 1,308 4.5 0

1.038 c

II. P.

• Q.A.

6,480 32,999 32.4 0

50.960 c

ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 30,991 0

53.897 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 0

4.858 N/A

'l'ASK DESCRIPTION Craft Support and Security Project Supervision and Administration Visitors and Inspectors Subtotal Phase II (Completed '!'asks Only)

ESTIMATED LABOR MANllOURS 57!422 TABLE l PERSONNEL RADIA'l'ION EXPOSURE

SUMMARY

PHASE II - REMOVAL ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR EXPENDED ES'l'IMATED TO - DATE EXPOSURE MANllOURS (MAN-REM Not lleported 190,601 559.6 l

PAGE _8_ OF J]_

ACTUAL EXPOSURE ACTUAL EXPOSURE TASK FOR REPORTING EXPENDED STATUS PERIOD

'fO - DATE (C=COMPLETE)

MAN-llEM MAN-REM)

I=IN PllOGRESS 0

1.281 N/A 0

37.579 N/A 0

0.300 N/A 1.341 699.641

TABLE l PAGE _9_ OF _JJ_

PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE Ill-INSTALLATION ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ES'l'IMATED FOR REPOR'l'ING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOU TO - DATE (C-COMPLETE)

DESCRIPTION

~MANllOURS~

~HANllOURS~

~MAN-REM)

(MAN-REM)

(MAN-REM)

(I-IN PROGRESS~

Steam Generator Lower Shell Installation l,926 ll, 723 9.63 1.918

15. 744 c

Installation of Reactor Coolant Piping 6,768 90,167 67.68 18.968 326.759 I

Steam Generator Girth Weld 5,400 41,614 27.0 2.296 17.357 c

Installation of Main Steam Piping 3,735 12,946 18.68 3.214 17.299 c

r Installation of Feedwater Piping 2,700

7. 727 13.5 0.523 3.985 c

Installation of Blow-down and Miscellaneous Piping l,782 21,528 17.82 32.050 83.740 I

Install Steam Generator Level Instruments 2,592 14,016 12.96

• 14.399 17.171 I

Installation of Insulation P,562 3,483 57.81 2.967 4.255 I

Temporary Scaffolding 7,500 15,282 75.0 6.093 39.298 c

Temporary Lighting

& Power 5,250 13,494 26.25 0.834 8.795 c

Ii TABLE 1 PAGE 10 OF 13 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE III-INSTALLATION ACTIVI'rIEs i

SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK I.ABO!{

TO - DATE EXl'OSURE PERIOD TO - DATE (C=COMPLE'l'E)

DESCRIPTION (MANllOURS)

(MANHOURS)

(MAN-REM)

(MAN-REM)

(MAN-REM)

(I=IN PROGRESS)

Cleanup and Dec on 17,000 58,820 85.0 18.801 96.704 c

Polar Crane Operator 1,500 3,205 4.5 0.192 l.252 c

11.P., Q.A.

6,480 84,517 32.4 6.847 55.684 c

ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 38,739 2.453 18.999 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 1.091 5.783 N/A Crsf t Support and Security 0.311 1.390 N/A 1'

Project Supervision i

and Administration 11.236 79.628 N/A i

Visitors.and Inspectors 0.029 0.329 N/A Subtotal Phase III (Completed Tasks Only) 51,491 288,067 291.96 55.838 362.247

TABLE l PAGE 11 OF 13 PERSONNEL RADIATION EXPOSURE

SUMMARY

PHASE IV - POST INSTALLATION AND STARTUP ACTIVITIES SURRY POWER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXPENDED ESTIMATED FOR REPORTING EXPENDED STATUS TASK LABOR TO - DA'l'E EXPOSURE PERIOD TO - DATE (C=COMPLETE)

DESCRIPTION (MANllOURS)

{MANllOURS}

(MAN-REM~

(MAN-REM)

(MAN-REM~

~I=IN PROGRESS}

Install Biological Shield Wall

l. '!40 557 16.2 0.079 0.186 I

Repair Crane Wall Opening 4n 336 2.37 0.008 0.400 c

Repair Pressurizer Cubicle Wall (See Note 2)

Install Steam Generator Recirculation and Transfer System 9,000 36,966 90.0 7.438 67.610 I

Remove Reactor Cavity Cover 130 166 0.65 0.042 0.072 c

Install Reactor Cavit~

Coaming 240 773 1.2 0.692 0.692 c

Reassemble Manipulator Crane 1,176 882 23.25 0.419 0.723 c

Remove Steam Generator Transport System 425 143 2.12 0

0.187 c

Reassemble Shroud Cooling System 576 3,430 11.52 3.462 3.822 c

Hydrostatic Tests 75 1,643 0.38 2.316 2.316 I

Temporary Scaffolding 7!500 1,573 75.0 2.611 4.064 I

1; TABLE l PAGE ____l2_ OF _u_

PERSONNEL RADIATION EXPOSURE

SUMMARY

PllASE IV - POST INSTALLATION AND STARTUP AC'flVI'flES SURRY POIJER STATION-UNIT NO. 2 ACTUAL LABOR ACTUAL EXPOSURE ACTUAL EXPOSURE TASK ESTIMATED EXl'ENDED ESTIMATED FOR REPOR'rING EXPENDED STATUS TASK LABOR TO - DATE EXPOSURE PERIOD TO - DATE (C=COMPLETE)

DESCRIPTION (MANUOURS)

(MANllOURS)

(MAN-REM)

(MAN-REM)

(MAN-REM)

(I=IN PROGRESS)

Temporary Lighting

& Power 5,250 1,311 26.25 0.357 0.638 I

Cleanup and De con 17,000 7,048 85.0 8.057 11.611 I

Polar Crane Operator 1,500 487 4.5 0.082 0.097 I

Painting 9,000 1,405 45.0 3.282 3.282 I

H.P., Q.A.

6,480 10,767 32.4 2.933 4.427 I

ADDITIONAL TASKS Material Handling, Equip-ment Maintenance, and Miscellaneous Construction Activities 3,768 1.051 1.594 N/A UNASSIGNED PERSONNEL CATEGORIES Engineering Support Not Reported 0.468 0;618 N/A Craft Support and Secµrity 0.133 0.201 N/A Project Supervision and Administration 4.815 7.957 N/A Visitors and Inspectoi;s 0.013 0.022 N/A Subtotal Phase IV (Completed Tasks Only) 3,020 5, 730 41.11 4.623 5.896

TABLE l PERSONNEi. RADIATION EXPOSURE

SUMMARY

PUASE V - STEAM GENERATOR STORAGE ACTIVITIES SURRY POWER STATION-UNIT NO. 2 PAGE 13 OF 13 TASK TASK DESCRIPTION ESTIMATED LABOR (MANIIOURS)

ACTUAL LABOR EXPENDED TO -

DATE (MANHOURS)

ESTIMATED EXPOSURE (MAN-REM)

ACTUAL EXPOSURE FOR REPORTING PERIOD (MAN-REM)

ACTUAJ. EXPOSURE EXPENDED TO - DATE (MAN-REM)

STATUS (C~COMPLETE)

(I=IN PROGRESS)

Steam Generator Storage Activities 300 3,659 35.0 TABLE NOTATION 0.174 5.054 c

l.

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, II, and III. They are not included in the Subtotal Values for Phase IV (See Report Section 2.3.c).

TABLE 2 PAGE _l_ OF _4_

SUllltY l'OUtm S'f'/\\'l'J.ON STE/\\11 GENllnA'IOR ltlll'LACIWENT PltOJECT lll.U'Oil'f OF JlADlO/\\CTIVE EFFLUENTS

• YEAR: __

""'"l-"-9""'79'---

~~~-_-

I.

1.ll)UIO RELEASES

.. ~

UllITS Curies Iuotopes Released HPC l!Ci/ml I-131 3 x 10- 7 I-1.32 8 x lQ-6 J-l]J l

JC 10-6 lO-s I-1)4 2 x 1-135 4 x io-"

Cs-1311 9

10-*

x 2.JOE-3 Cs-lJ7 2 x 1.0-*

4.OOE-l Co-57 4 x 10-1 2.20E-5 Co-58 9 "

lo-,

5.00E-4

_.G!d!O 3 Ii w_-s L21E-2 Mn-SI, l x rn-~

4.90E-4 Na-211

] x i?

Cr-51 2 i: 10- 3 Fe-59 5 x 10->

iib-'~5 l x 10-~

1.88£-4 Sb-1211 2 x 1 o-=1i SL-125 1 x 1*

3.60E-5

-1.!!:"65 1 x io-'*

2.67E-5.

_-1.r.::25 67io=-s Mo-99 4 x 10-5 Ru-103 8 --;;:-10,

l.65E-6 n-xe-1)3 10-*

a x AtilOm 3

10-S x

9.79E-11 Nl-63

] x 10-s Fc-55 8 x lo-*

].12E-J Ce-144

)

1: 10-s 2.92E_:~

1--'fc-99111 3 K 10-3 Ce-141_

2 ic.rn:~

4. 251\\- 7 Vol 11111e of l.iq ui d to llischaq~e Canal Liters H.9UE+:>

• Not Detected

• "' Sample analysis results not yet receive<! from service vendor.

Upon receipt, analysis data will be submJ.tted as a supplement to this. report.

h*Includee R.~dioact.ive Liq*uid Waate genoratod during a1 outage

<=sm*r-.

~~~~JiE!~=t-~2~~!!!!~~[=*

.~~~

......_, --l----,-----

-....,,,...~..

-**--==-*~~

t==

=~~~

~--~~~-'--;~'~T~*~:

I l

I I

e il

{

il ii

~

ii

~

=1 1.00E-4 3.00E-4 l.81E-3 I

"2:70t:-J

l. l10E-3 4.02E-J D

I

--r.:IDE=r-5.00E-6 k

I I

-T~OOE-J S.OOE-4 6.02E-J i

5.20E-3

4.40E-3

4. 21E-J D:7int~::r-l.60E-:5 l.JOE-4

-~--- -

w---

11. 56E-6

--"*---. **-r:nr-s--

I I

• 'l

• I lit

~----

I 9.88E-7 I

I

~

~

3.22E-2

>---u-----*

_1_,_!t.l~.

r-

~

-Lru::- L __ l'".li4~ ~-u*

I

• ~---.____.------

~ :---i----,.---

IT~

~

I

i. 9~ri:o--

-u--*

~

I 7..li6l!+5:)9.117E+f __.

I

I.

1,,

\\

1\\

\\ *.... -.

11.

AlllBORNE llELEASES TABLE 2 Sl!Rlt'l POlllill STATION STEAll GEllERATOI\\ REl'LACl:'.HENT PllO.IECT llEl'OllT OF RADIOACTIVE EFFLUENTS

. PAGE 2

OF 4

YEAR: ___

l-"-9""-79'---

_____(~_)_f.1.I.!.iJ:.ulate.._~------------~----t-~,.-~==---,.--t,,------*N-,,...-----t*-.,.--~

Cs-Ll!t

• - _8.83E-6 1 571l-6

'.l..08E-6 7:36ir-:r-4 _____

1 _________ --ll-------

Cs-137 r.riill.CS-- _l_..fillE=,L

l. 51,£::.S- --r.Gili!::S-Cr-51

~

• ---11-~~*-~~--ll------ii------~-----i--------

Co-58

~

7.j_liE-6 _

_LllE-6 J.52ll-6

, ___ c.o-60 5.74E-5 4..J!J~-5 3.311!-S 4.171!-5

• ---~~Jn::.'.iL

5. 79E-7 Ii------ ------*-------i+------+-------

Fe-59 (b) Halogens l-lJ~l _______________,11-----11---*~---11--"----r---*---..---*---

I-U2 6----~

1 -11'.L___. ______________ tr-----11*--:----'I---*---

~

I-1 'll A

I-13~

~ *

(c) Gases 1

Xe.-113

---*-----~------ff------~------it--------

u----"X~e._-l.J..cm1'"--------------n----11*--*-*---t1--*----~--*----11----*-

Xe-11~5---------------r-----v--,*----~--*,.-----~--*----1---"'..----u------K-------'l-------ti--------

Kr-85111 io Kr-65 Kr-87 1 ___ _.,.Kr.::.8~6----------------

Ar-111

,~

llL

... 1Ul.Ll!Lfu\\DlfiACT.UllUWITE~.----H-------*------*------11----1I __ _

(a) Total Amount Soll<l Haste I

Packaged l'l' 3

8. 70E+3 L66E+3 2.0JJN-3 1.25E+J

-Cb) llstimate<l Toral Activity Curies ~~

• i.26"'1H~0~-*-1-.-1-o-1H-O-.--*.*r:1urF2--*-----

u--(-c_)_D_a_te_o_f_S_h_i_p_m_en_t_a_o_d _ __,_ ______

-'l----1i~8-a-n-1weII-, -. Barnwell,

,llai:-nwel 1,

-Dai:-~i;7i:i11-, -

---

~1-------11------~-------

0l spos i tion S.C.

S.C.

S. C.

S. C.

~~~-=--~=~--=-*~==~c~~*=*

• ~,*~-=c*11-n9~= ~9-*

_..,..,12"""'-""'

79"""---""'jl):]i:."']9=-~

"f'::l".:."79'"'~*=**--===-~-~--~~-"=~~~-""'~=~~,~~-

U-10-79 9-25-79 10-9-79 8-17-79 10-10-79

• Not Detected 8'421-79(3)

B-28-79(1,)

TABLE 2 SUIUlY l'Ol~ER STATION STEAfl GENERATOR ltEPl.llCEtiEHl' PltOJl!CT llEl'OllT OF R/\\DIO/\\CT1Vll EFFLlll'NTS YEAR;, __

_:;lc.=.9-'-7~9 __

2.76E~5 4.62E-4

---il."2~-

-~

---1-~:..::.:;.:c...:; __

~_,_.-==.=-~-*--.

,~,...-----*-~.. ~--~11---~*-~--1 I<

'ii

• ~

fi 3 21E-1 2.23E-3 2.4JEJ-3

.L.J~E-J 2.11JE-]

2.20E-3 7:24E-3 5.90E-J 5.B2E-3 3.97E-3 6.20E-J

"'7.90E-l 5.54E-6

-1J.!E-6 9.00EJ-S 4.00E-6 2.15E-2 1.15E:r-3.47E-2 7.90E-3 6.loE-3 l.601l-J 2.03E-2 9.091l-3

--r.7'~ 6.lOH-3 l.lOE-r-830E~

l.28E-3 3.l,2E'-4

-r.'.12~ l.34E..:Y-- -r.Jli~ ---r.2~

1.IOe-5 5.55E-3 6.40E-4 3.40El-3

--r30E-2

--Z.uu..,,-:>

1. 42El-6

-~.-----

-r:9iiE-4

8. 81E-5 2.52~

• S.60E-5 L. /U~.-:>

-2:-IliEFl- ----r.:fOEl-4

---r.2jif:T ii

--r.n£::;i- --r.5'0E-S

• -,(

-wK----1

---

II--- --r.JIE-5-,-

4.06E-6

--;r:-700=5- -rIDIF5

-r.iilJ~ -r.:Jmr-s---

7.filE --.-----

l.54El-4 5.20E-5 5.92E-5 7.41lE-6 2-94f:l-5

--,.----I I.161l-6

--~-"---""-='-----.....::.-=--:c::.---------11---1-*...:9::..:*...:4:.::2:::.ll_-;;:.5_-_ -_*. _::""'T.19E-4--

• ~--------ii----ll---*----* 2.66E-5 1.'2.fE-5

---,-::------~_;__;;;=-~-------1-----1--'3~*c...:'*..:.6=-E--'l'--- J:"Il~ ~~

3.55E=l__'._ ~E-3 li."57E-3 i-~"--"-=-------'~~"---------'----ii__:l:..:*.::::.0.:.:7E=.--=2:... ___ 6,13E-2 l.25E-2 7.BBE-3 l.61E-2 L'28E-3 ir---~------~~"'---------1-----ll---*~---u-;;..9.;..:.5:..:9.::ll;_-.:c6 __ 1 2.lSEl-6

--X 5.581l-6

1. 351l-4

-ii

---*---*--- t,:TI~ *

~--:-flilFo-t---Vi;:-0*1-ure--o'fc-:L".ior--1uird..--:-to---:D""l-s-,cl'-lar-:-qe-.,C~an-al.-----l'-.L~1.t-;er-s-1-S:-91~ IT.Tfiffii-- -9:0UBF5"~--l--,.Lr.T'T1

.lllil:'.l*-f °'*u:---l--.1-. I"S"'EOT+'6-l-c9","9""3"E+-;-;5,-----I

• llol:. Oetected

• • S<Ulple analysis results not yet recelvErl from service 11,/efulor.

~Jon receipt, analysis data will be slilmi.tted as a suppleua1t to th.is report.

"'**InclU<les Radiooct.ive Liq*uid Uaste generated during 01 outage PAGE _3_ OF 4 -

\\..

II AlllBORNE REI EASES Xe-1J3 Kr-87 TABLE 2 SUllllY l'Olllm STATION STEAll c:mmMTOll lllll'l.ACEl*ll:H'r PltO.IECT

!ii:1'onr OF U.AlllOACTIVE EPFLllENTS

9. 6ltE+l J.OOIHO Ti if Ii PAGE _4_ OF _4_

• YEAR '---"l_._9~79"---

7i

___ K.--1111 A~r-~4 1ul'--------------~

u--------------------~11---4---~*---~-----11------1------**-----*------*

llL...Jilll.lll....RAfll.UAC1'.lJlE...ILlllS£ilSAl~---11-----1-----*------*------11-----*-----~------*

(a) Total Amount Solid Waste Packaged FT 3 l.65E+3 l..llE+4 6.92E*t-3 6.600~3 9.30E+3

7. 76E+3

'(b) Estimated Total Activity Curi.es 9.9l1E-l J.16E+O

-:Z:76Iilfr-- -'L5'.3EffIT7"" -i-:-o:m+i-63e=E-t~-O~-..j

--Wn,;te of Shipment and lluniwcll, llapiwell, Bari~ell, Barnwell, llarnwell, llaffiweIT;--

IJlsposltion

.Ji" s.c.

S.C.

S.C.

_s_._c __. ___

1

=..,,~

-=. =..--~~~~~~~~ 2-20-19J-6u79 - J-17-79= 4-*6:_79 (4) ~s:-7~- * *+-1'!1~~* * =1'~1~*

2-22-79 3-7-79 J-19-79 4-9-79 5-ll-79

6-7-79(3) 7-10-79

• Not Detected

(+) June date of ehlpuicnts continued

• 6-25-79,6-26-79,6-27-79 2-27-79 3-6-79 J-:20-79 4-12-79 (2) 5-16-79 6-6-79 7-13-79 2-211-79 J-13-79 3-26-79 4-14-79 5-19-79 6-13-79 7-16-79 3-13-79 3-29-79 4-17-79 5:<;23-79(2) 6-14-79 7-18-79(2) 3-15-79 J-29-79 4-22-79 5-25---79(2) 6-15-79(3) 7-20-79 5-29-79 6-22-79 7-23-79 5---30-79(2) 6-?4::-N 7-20-79

(+)

-~*1