ML20132E505

Rev 3 to TMI-2 Recovery Program Estimate

ML20132E505
Person / Time
Site:	Three Mile Island
Issue date:	08/31/1985
From:	Kintner E, Santee L, Standerfer F GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20132E475	List: ML20132E473 ML20132E505
References
NUDOCS 8510010102
Download: ML20132E505 (62)

Text

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'TMI-2 RECOVERY PROGR AM ESTIM ATE

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REVISION 3 August 1985 4

PREPARED BY:

d L. G. Santee Manager, Program Controls CONCURRED BY:

'F. R. Standerfer

[

Director, TMI-2 8510010102 850923 APPROVED BY:

J,o ADOCK 0 % 3 O E. E. Kh1Tner~ v ~

v PDR P

Executive Vice President

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TABLE OF CONTENTS TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 Page Introduction.......................... 1 Table 1 - Assumptions and Qualifications...........

7 Table 2 - Work Breakdown Structure Summary Cash Flow.....

13 Table 3 - Program Cost Sunnary by Organization........

14 Table 4 - TMI-2 Program Master Schedule Milestones......

15 Appendix A - Chronological Summary of Recovery........

17 Program Estimates Appendix B - Summary Listing of Program WBS Elements.....

21 Appendix C - Defueling Activity Summary 22 Appendix D. Decontamination & Dose Reduction Activity Sunnary. 31 Appendix E - Level-4 WBS Cost Detail.............

48 Appendix F - Potential Unplanned Workscope..........

55 Appendix G - Program Staffing Plan..............

57 Appendix H - TMI-2 Projected Waste Generation Sunnary....

58 Re fe re nc e s..........................

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TMI-2 RECOVERY PROGRAM ESTIMATE REVISION 3 INTRODUCTION Purpose In January 1985, GPU Nuclear Corporation initiated a review of estimated costs to complete cleanup operations at TMI-2 as part of an on-going program to plan, manage, and perfonn defueling and decontamination operations for the accident-damaged TMI-2 facility. This report sumarizes the results of that review.

Sumary The program cost is, for practical purposes, unchanged from that forecasted in the Recovery Program Estimate, Rev. 2, December 1982 and the TMI-2 Defueling Study, August 1984. Activities to defuel the reactor vessel and associated systems, to remove or imobilize radioactive materials, and to complete end point verification are forecast to be completed in September 1988 at a total program cost (1979-1988) of

$965,000,000.

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Background===

Since the March 28, 1979 operating accident, several TMI-2 Recovery Program Cost Estimates have been prepared. Appendix A presents a chronological sumary of these estimates.

this report represents a revised estimate based on known plant conditions through June 30, 1985.

It incorporates knowledge, planning, and experience gained since the last complete review of the program, as documented in the TMI-2 Recovery Program Estimate, Rev. 2, December 30, 1982 (RPE, Rev. 2), and as supplemented by the interim cost assessment, the TMI-2 Defueling Study, completed in August 1984.

Significant new information concerning plant and reactor fuel conditions has been acquired since the TMI-2 Defueling Study was prepared. The removal of the reactor vessel head in July 1984 provided the first direct inspection of vessel internals and video inspection of areas below the damaged reactor core. The plenum was removed in May 1985, permitting the first examinations of limited regions of the core support assembly 03/30/85

i RPE, REV. 3 INTRODUCTION Page 2 of 6 (CSA).

In addition, remote radiation surveys were conducted to (1) detect the presence and determine estimated quantities of fuel external to the reactor vessel and (2) measure the radiation fields in the reactor building basement (E1. 282').

Information obtained as a result these activities has increased our confidence that planned activities will accomplish desired results; i.e.,

safe defueling of the reactor while maintaining the plant in a stable and safe condition. However, uncertainty remains regarding actual defueling operations, particularly their estimated durations, because of their first-of-a-kind nature. Further, post-defueling workscope (e.g. decon-tamination and waste management) is sensitive to Phase III completion criteria.

Actual program costs may vary from those forecast in this report because of revised criteria or new data affecting assumptions.

This estimate contains an identified amount considered to be sufficient to reasonably manage the known risks.

Approach Used in Developing the Estimate In developing this estimate, program objectives, organization and completion criteria, as well as specific technical plans for accomplishing program objectives were reviewed and revised to incorporate current information and planning as of June 30, 1985. Tasks required to accomplish current program plans were identified, categorized within the program work breakdown structure (reference Wcek Breakdown Structure, TP0/TMI-116), and their cost effects assessed.

Costs for planned activities for which no changes were identified were carried forward from the TMI-2 Defueling Study.

For non-level-of-effort tasks such as those contained in defueling and decontamination operations, the type, quantity, and duration of labor, both direct and indirect, and the material and equipment needed to accomplish each task were identified, with the appropriate pricing applied. These components were sunmarized to provide an estimate of cost for a given task.

Level-of-effort tasks, i.e., program support and plant stability / safety, were estimated based on program historical data adjusted to reflect planned changes in program requirements.

These changes, in part, include a reduction in new systems engineering effort beginning in 1986, an increase in decontamination operations activity also beginning in 1986, and a planned license conversion in mid-1987. 08/30/85

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RPE, REY. 3 INTRODUCTION Page 3 of 6 Organization of Estimate This report is organized around two primary sections: (1) a brief description of estimated workscope (Estimate Bases) and (2) Assumptions and Qualifications (Table 1) including sumary reports of program costs (Tables 2 and 3) and the schedule to accomplish the work (Table 4).

Several appendixes support the two primary sections.

Appendix A provides information for comparison of this estimate with previous program estimates.

Appendixes B through D provide additional descriptions of program workscope; and Appendixes E through H provide supporting detail for program cost sumaries presented in Tables 2 and 3.

Costs, assumptions and qualifications, and financial exposures are organized according to the program work breakdown structure (WBS) presented in Technical Plan TP0/TMI-116, Work Breakdown Structure.

With the exception of the costs presented in Table 3, which is an organizational -sumary of project costs, all costs are associated with a program work element.

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The WBS is composed of six major work categories, each of which is made up of several elements. The six major work categories are as follows:

1 - Program Support 2 - Stabilization, Dose Reduction, and Decontamination 3 - Reactor Disassembly and Defueling 4 - Radioactive Materials Management 5 - General Recovery Facilities / Systems 6 - Plant Stability / Safety Further descriptions of work tasks that constitute a given WBS work element are provided in TP0/TMI-116. For convenience, a listing of program work elements is pn.:nted in Appendix B.

Estimate Bases Technical Plan TP0/TMI-115, TMI-2 Program Strateqy, describes the program workscope and completion criteria on which this estimate is based.

The recovery program is structured into three phases: Phase I -

Stabilization, Phase II - Fuel Removal, and Phase -III - Cleanup.

Phase I i s compl ete. Phases II and III are essential, relatively urgent, and unaffected by a decision as to the ultimate disposition of the plant.

Costs associated with the disposition decision are excluded from the scope of this estimate. 08/30/85

t RPE, REV. 3 INTRODUCTION Page 4 of 6 i

The overall objectives of the TMI-2 Recovery Program are to effectively remove the remaining risk to public and worker health and safety from potential releases of radioactivity from TMI-2, to monitor the plant, and to support a future decision to refurbish or decommission TMI-2. Whil e minimizing the radiation exposure during the program to the cleanup workforce, these objectives will be achieved when:

2 o The possibility of criticality is no longer credible.

o' The potential for fission product mobility has been eliminated for all practical purposes; i.e.,

1 radioactive water, airborne contamination, and loose surface contamination will be removed or controlled.

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4 o Fuel has been removed and shipped off site.

o Radioactive waste from the above activities has been packaged and shipped, or safely stored.

o Radiation levels are reduced commensurate with the need for access: (1) to permit continued plant monitoring and (2) to support plant disposition decisions.

o Water will be removed from plant systems and spaces and the potential for reintroduction of water will be preclu ded.

I o A safe, monitored plant condition is established.

The amount of fuel remaining at program end (completion of Phase III as 4

described in TP0/TMI-115) is governed by the prevention of criticality i

and fuel accountability requirements.

The intent is that as much fuel as practical will have been removed; i.e., bulk fuel will have been effectively collected and removed from the reactor and reactor coolant and connected systems. Some fuel contamination will remain within the plant systems and structures.

(See Appendix C for additional descriptions of reactor disassembly and defueling activities.)

I Phase II decontamination efforts will primarily support dose reduction for reactor disassembly and defueling, as well as ex-vessel fuel removal t

e fforts.

Additionally, some decontamination activities in the reactor and auxiliary and fuel handling buildings will be necessary to permit and maintain access for required safety surveillance operations and

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1 RPE, REY. 3 a

INTRODUCTION Page 5 of 6 maintenance, and to support establishing the radiological conditions of the plant at the end of Phase III.

In Phase III, decontamination efforts will be directed to removing or securing mobile radioactive materials that~ remain following completion of fuel removal activities.

(See Appendix D for additional descriptions of decontamination activities.)

At the completion of Phase III, plant systems will have been water flushed and drained.

All water will have been removed from the reactor building basement. High radiation areas will exist in the plant at the completion of Phase III; however, non-adhering contamination will have been removed or fixed.

Consistent with the objective of eliminating fission product mobility, there will be no liquid radwaste stored on site at Phase III completion.

Extended onsite storage of waste will be minimized.

Waste will be packaged and shipped to offsite disposal ~ facilities, either a commercial or U.S. Department of Energy (D0E) facility, depending on the nature of the particular waste. Abnormal waste disposal will be in accordance with the Memorandum of Understanding between the DOE and the Nuclear Regulatory Comission (NRC), March 15, 1982.

Plant components will be removed and shipped for disposal only when dictated by radiological control considerations, operational necessity, or clear cost advantage.

Components not removed at the conclusion of Phase III activities will be left in place.

However, many major items of defueling equipment will be removed.

Plant status and material conditions that will exist when the Phase III program objective is achieved do not represent the ultimate condition of TMI-2. Once a decision is made on the ultimate disposition of the plant, that decision will dictate the nature and scope of future, post cleanup activities.

Activities related to refurbishment or decommissioning of the plant are not within the scope of the recovery program as defined by TP0/TMI-115 and, accordingly, not within the scope of this estimate.

Sumary of Program Costs Table 1 lists the general assumptions and qualifications on which program costs were estimated.

Tables 2 and 3 summarize program costs by WBS element and organization, respectively.

The costs presented in Tables 2 and 3 include some provision for unplanned costs. Appendix F, " Potential Unplanned Workscope" identifies activities or events which have the potential for additional program costs. 08/30/85

RPE, REY. 3 INTRODUCTION Page 6 of 6 The current total program estimate listed in Tables 2 and 3 is

$965,000,000. Of this amount $561,000,000 has been spent as of June 30, 1985. The remaining $404,000,000 includes an allowance of approximately 10 percent of the 'to go' costs for unplanned workscope identified in Appendixes E and F.

For practical purposes the program estimate is unchanged from the previous progran 2 stimate, Recovery Program Estimate, Rev. 2, December 1982 and the TMI-2 Defueling Study, August 1984. 03/30/85

rw TABLE 1 TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 ASSUMPTIONS AND QUALIFICATIONS Reference Related Number WBS Element General 1

All The TMI-2 Program Strategy (TP0/TMI-115) is used as an overall basis.

2 All All work will be accomplished in accordance with the Program Master Schedule, August 1985, presented in Table 4.

3 All All costs are forecast in 1985_ dollars with escalation added based on a 5 percent annual increase in costs per year compounded.

4 All Resources required to support a decision on the future disposition of the plant have not been included in this estimate.

5 All No salvage value has been considered.

6 All Part 50 License is modified effective July 1, 1987, which is after the completion of in-vessel fuel removal.

7 All Licensing requirements, including public hearings, are limited in scope and do not delay work.

Stabilization, Dose Reduction, and Decontamination 8

227 Required work in the reactor building (RB) basement involves:

o Removing bathtub ring o Desludging l

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RPE, REY. 3 l

TABLE 1 Page 2 of 6 Reference Related Number WBS Element Stabilization, Dose Reduction, and Decontamination (cont'd.)

o Selective concrete removal o Gross decontamination via high pressure (HP) flushing, and/or application of fixing agents o Demolishing enclosed stairwell and removing rubble.

9 236 The TMI-2 fuel handling building will be decontaminated to prevent the spread of contamination from TMI-2 to TMI-1, 10 236 Auxiliary and fuel handling building ( AFHB) walls, floors, overheads, system exterior surfaces, etc., will be decontaminated to a degree that residual contamination is acceptable and/or stabilized by fixing agents. The AFHB Decontamination Plan (TP0/TMI-130) establishes the criteria.

11 243 After defueling, the reactor coolant system (RCS) will be water flushed, drained, and closed.

Costs for chemical decontamination are not included in the estimate.

12 243 Other RB and AFHB systems will be desludged, flushed, drained, and closed.

In general, no liquids, sludges bearing fission products or fuel contamination will be left in plant systems. Costs for chemical decontamination of these systems are not included in the estimate. 08/30/85

RPE, REY. 3 TABLE 1 Page 3 of 6 Reference Related Number WBS Element Reactor Disassembly and Defueling 13 326-7 The fuel condition is assumed to be as follows:

o Approximately 80-85 percent of the fuel is located in the core region. Of that amount, approximately half is readily removable by vacuuming and " pick and place" methods (i.e.,

no size reduction, mining, or other aggressive removal techniques are required for this portion).

The balance consists of material in various physical l

forms, including agglomerated sections, all of which is extractable using strong mining tool s.

o Approximately 15-20 percent of the fuel is no longer in the core region.

Nearly all of this is in the lower head region, in and l

below the CSA. Much of this material can be removed by " pick and place" and vacuuming methods; however, some may l

require more aggressive methods (breaking,

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separation, size reduction) to permit removal.

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o The balance of fuel (perhaps 1 or 2 percent of the total) is distributed throughout the RCS, primarily in the steam generators, J-legs, pressurizer, and surge line.

Essentially all of this material consists i

of small particles removable by vacuuming or other mechanical methods, i

14 386 Each canister can be loaded with core debris to an average 1500 pounds; an average of one canister per day can be loaded.

15 386 In-vessel fuel removal working area radiation field will average 15 mr/hr and worker dose limits will average 1 rem /qtr. 08/30/85

4 RPE, REV. 3 TABLE 1 Page 4 of 6 Reference Related Number WBS Element Reactor Disassembly and Defueling (cont'd.)

16 386 Access for ex-vessel fuel removal will be gained through various system entry points, based on characterization results. Access to the cold legs may be gained through holes cut in the CSA upper core barrel. The RCS water level can be lowered after bulk fuel removal to pennit removal of the four reactor coolant pump motors.

17 388 Fuel accountability by conventional means and to normally established standards of precision is not possible because of the condition and distribution of the damaged fuel.

Therefore, an accountability plan has been developed which is based primarily on a post-defueling survey of the plant which will establish, within practical limits, the quantity of fuel remaining in the plant.

(Reference Technical Plan TP0/TMI-035, August 1985, TMI-2 Core Accountability. )

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The CSA will be defueled in-place and remain 426 in the vessel but may require cutting to gain access to fuel integral with the flow baffle structure and to gain access to the lower reactor vessel head.

Radioactive Materials Management 19 400 Costs for waste shipping, handling, packaging, and processing are based on war.te generation projections contained in Apoenu t H.

20 422 Facilities / procedures will w 1.1 place to accommodate onsite packagin.;, twdling, and interim storage of all solid waste (dry active 08/30/85

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RPE, REV. 3 TABLE 1 Page 5 of 6 Reference Related Number WBS Element Radioactive Materials Management (cont'd.)

20 422 waste and waste concentrate liners).

(cont'd.)

Low-level wastes will be disposed of at an off-site, low-level waste disposal facility.

21 424 Contaminated pennanent plant equipment will not be removed from the plant unless necessary for dose reduction or as required to avoid congestion within critical work areas.

Defueling or decontamination systems determined to be of no benefit to future work will be removed from the plant.

22 4 31 All water in the plant will be processed by existing or planned systems (EPICOR II, SDS, boron recovery evaporator (BRE), DWCS).

An allowance is included for the engineering, licensing, and implementation of water solidification and site storage. No allowance has been included for disposal costs.

23 426 The reactor vessel head will remain stored and shielded during defueling and will be replaced on the reactor vessel after defueling.

24 426 The reactor plenum will remain stored during defueling and will be reinstalled in the vessel after defueling.

25 442 All abnormal waste will continue to be disposable via the 00E.

26 442 All recovered fuel will be canned and shipped.

27 442 No more than 288 canisters (fuel, knockout, and filter) will be required to complete defueling. 08/30/85

RPE, REV. 3 TABLE 1 Page 6 of 6 Reference Related Number WBS Element General Reactor Facilities / Systems -

28 500 There are no future permanent facilities included for TMI-2. An allowance has been provided for the design and installation of isolation, protection, and surveillance systems which should be adequate for several years._ Operation of the systems is excluded.

Plant Stability / Safety 29 600 Equipment facilities, etc., will be maintained in accordance with licensing requirements.

Access to areas will be controlled as required for radiological protection.

30 600 Maintenance of equipment and facilities as investment protection or for preservation of future disposition options is excluded.

. 08/30/85

TABLE 2 TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 WORK BREAKDOWN STRUCTURE SUMARY CASH FLOW (5 x 1000)

WBS Description 1985 1986 1987 1988 Total 1

Program Support 51370 48140 37690 23780 160980 2

Decon & Dose Reduction 4865 21975 32000 24920 83760 3

Reactor Disassembly &

43035 23225 17625 1000 84885 Defueling 4

Radwaste Management 8590 14500 23250 17015 63355 5

General Recovery 270 2'000 2000 4270 Facilities / Systems 6

Plant Stability / Safety 12600 12150 10735 7475 42960 TOTAL (1985 dollars) 120730 119990 123300 76190 440210 i

Escalation Factor 1.05 1.103 1.144 Escalated Total 125990 136000 87161

~ Use 120700 126000 136000 87200 469900 i

PROGRAM COST - 1979-1984 495000 PROGRAM COST - 1979-1988 964900 l

l Use 965000 08/30/85

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l TABLE 3 TMI-2 RECOVERY PROGRAM ESTIMATE REVISION 3 PROGRAM COST SU MARY BY ORGANIZATION

($ x 1000)

Organization 1985 1986 1987 1988 Total Office of the Director 600 600 550 250 2000 Program Controls 1280 1000 800 200 3280 Recovery Programs 59200 55620 61040 34220 210080 Site Operations 17600 22260 30450 22360 92670 Technical Planning 4000 2700 1300 200 8200 Licensing & Nuclear Safety 3300 3300 2100 800 9500 Government & Industry 970 970 600 2540 Programs TMI-2 DIVISION 86950 86450 96840 58030 328270 Support Divisions 33780 33540 26460 18160 111940 TMI-2 PLANT (1985 dollars) 120730 119990 123300 76190 440210 Escalation Factor 1.05 1.103 1.144 Escalated Total 125990 136000 87161 Use 120700 126000 136000 87200 469900 195,0q0 50 0 PROGRAM COST - 1979-1984 PROGRAM COST - 1979-1988 964900 Use 965000 1

1 08/30/85

.a TABLE 4 TMI-2 RECOVERY PROGRAM ESTIMATE REVISION 3 TMI-2 PROGRAM MASTER SCHEDULE MILESTCNES 1.

Remove Plenum May 1985 2.

Start of Early Defueling October 1985 3.

Complete Fuel Shipping Preparations March 1986 4.

Complete Bulk Defueling September 1986 5.

Complete Upper CSA Defueling April 1987 6.

Complete Ex-Vessel Defueling May 1987 7.

Complete In-Vessel Defueling June 1987 8.

Complete Fuel Shipping April 1988 9.

Complete Systems Decon July 1988 10.

Complete Phase III End Point Verification September 1988 L

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APPENDIX A TMI-2 RECOVERY PROGRAM ESTIMATE REVISION 3 CHRONOLOGICAL

SUMMARY

OF RECOVERY PROGRAM ESTIMATES

($ x Millions)

Date of Estimated Program Estimate Estimate Completion Date Program Costa TMI-2 Recovery August 1980 October 1985 855 Program Estimate TMI-2 Recovery Program July 1981 December 1986 1034 Estimate, Rev. 1 TMI-2 Recovery Program December 1982 June 1988 975 Estimate, Rev. 2 TMI-2 Defueling Study August 1984 September 1988 967 TMI-2 Recovery Program August 1985 September 1988 965 Estimate, Rev. 3 i

NOTE:

a The TMI-2 Defueling Study August 1984, and the TMI-2 Recovery Program Estimate, Rev. 3, August 1985, are the only two estimates with scopes that are directly comparable. The narrative that follows briefly describes the most significant scope differences between the different estimates.

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RPE, REY. 3 APPENDIX A Page 2 of 4 TMIi2 Recovery Program Estimate, August 1980

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The August 1,1980 Recovery Program Estimate constituted the first formal estimate of the TMI-2 cleanup and recovery program.

It incorporated an assessment of plant conditions as of June 1980, a work plan and schedule that benefited from program experiences of the preceding 16 months, with an evolving understanding of the magnitude and complexity of the Recovery Program. One reactor building containment entry had been completed before the preparation of this estimate.

The estimated work scope encompassed cleanup through reconstruction to pre-accident conditions, refueling, and testing. The program end point (comercial operation) was scheduled to be attained in October 1985.

Base operations and maintenance were excluded. Funding limits were not addressed in the estimate.

TMI-2 Recovery Program Estimate, Rev.1, July 1981 The Recovery Program Estimate was revised in 1981 to reflect changes in program strategy and schedule. The original program logic concentrated the early effort on cleanup of those portions of the TMI-2 plant external to the containment building. Operations in the AFHB were thought to be less demanding than those that would be ultimately required inside containment. Thus, early operations were planned to serve as training for later, more difficult, in-containment tasks.

The Revision 1 estimate was based largely on data used for the August 1980 estimate, with some scope and estimating adjustments made to incorporate experience and data acquired since the August estimate.

The estimated work scope encompassed defueling.and decontamination to levels approximating those found in typical operating plants. Base plant operations and maintenance costs were included in the revision. Fuel loading, comissionirg, and/or decomissioning costs were excluded.

Seven containment eatries had been completed before the preparation of the Revision 1 estimate.

The revised scheduie had as its goal the earliest possible access to the reactor head to conduct in-reactor inspections and then lift the head i

from the reactor. The underlying logic for this plan was to obtain data as early as possible, to have adequate time to design the special tools and equipment necessary for removing fuel, and to assess any additional problems. 08/30/85

I RPE, REV. 3 APPENDIX A Page 3 of 4 j

TMI-2 Recovery Program Estimate, Rev.1, July 1981 (cont'd.)

In addition to the above schedule modification, the revised schedule l

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reflected the reduction in program level-of-effort which occurred in l

September 1980, and identified the program end point as December 1986.

The estimate did not, however, continue the reduced program level of l

effort through to the program endpoint.

It assumed that the program completion would be unrestricted by funding beginning in January 1982.

TMI-2 Recovery Program Estimate, Revision 2, December 30, 1982 The Recovery Program Estimate was revised at the end of 1982 to reflect continued program funding constraints.

In contrast to the Revision 1 l

assumption of unlimited program funding beginning in January 1982, the i

Revision 2 estimate included five funding scenarios. The scenario chosen i

to be the basis for planning purposes had $76 Million for 1983, $100 s

Million for 1984, $117 Million for 1985, $126 Million for 1986, $136 Million for 1987, and $81 Million for 1988.

The program end point was 4

extended to June 1988.

j Cost estimates were largely based on Revision 1 data adjusted for schedule and work experience gained over the activities of the preceding 16 months.

The estimated work scope encompassed defueling and decontamination to levels approximating those found in typical operating plants. Base plant operations and maintenance costs were included in the i

revision.

Fuel loading, connissioning, and/or decommissioning costs were excluded. Three remote camera inspections of the reactor core and approximately 130 containment building entries had been completed before preparation of this estimate.

i TMI-2 Defueling Study, August 1984 Delays associated with the polar crane refurbishment encountered in late

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1982 and 1983 caused the recovery program schedule to slip approximately

.1 year in 1983.

In early 1984, management decided to recover lost time.

An effort was initiated to develop a program in which reactor defueling j

activities would be accelerated to approximately coincide with the Recovery Program Estimate Schedule, Rev. F, dates contained in the TMI-2 i

Recovery Est' mate, Rev. 2, mentioned above. This effort included refinement of defueling concepts and, in parallel, a reevaluation of l

program. strategy and completion criteria.

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RPE, REY. 3 APPENDIX A Page 4 of 4 The TMI-2 Defueling Study was initiated to assess the cost impacts of "early defueling" and revised program completion criteria. The work scope estimated encompassed defueling and decontamination to support defueling, Phase III completion criteria, and those inspections and surveys appropriate to make a decision on ultimate plant disposition.

Base plant operation and maintenance costs were included in the estimated work scope.- Fuel loading, commissioning, and/or decommissioning costs were excluded.

Like previous Recovery Program Estimate revisions, the TMI-2 Defueling Study was not a " bottoms up" estimate, but rather a review of the previous Recovery Proc ram Estimate, Rev. 2 with revisions incorporated to reflect current conc.itions.

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APPENDIX C TMI-2 REC 0VERY PROGRAM ESTIMATE . REVISION 3 DEFUELING ACTIVITY

SUMMARY

Figure C-1 summarizes planned defueling activity logic and workscope through prog *am completion in 1988 to accomplish program objectives. The following paragraphs, cross referenced to specific activity boxes on Figure C-1, briefly describe the nature of the identified activities. Block reference numbers appear first followed by WBS numbers. 1-391 - B&W Planning Study - This study, prepared by Babcock & Wilcox (B&W), examines defueling methods and recommends inspections and defueling methods for the lower CSA. 2-391 - CSA Defueling Technical Plan - This technical plan will establish defueling inspections to be performed, tooling functional requirements, and tooling selection methodology. It will also establish defucling sequence and logic. 3-386 - Upper CSA Defueling Method Selection - Based on upper CSA examination (reference Block 8-386) and technical plan recomendations, the areas to be defueled, the necessary tooling development, and the required procurement will be identified. ~4-381 - Upper CSA Tooling: Engineer, Deliver, Install, and Test - Tools identified in Block J-486 will be developed, installed, and tested, including mockup installation and training before actual RB installation. 5-386 - Lower CSA Inspection - The following video inspections are planned for the lower CSA: o Incore guide to flow distribution welds l o Inserting camera through flow holes and examining the f area between the flow distributor and i,ncore support plate o With a fiber optic scope inserted through flow holes in the lower grid periphery via the fonner plates determine (1) amount of debris between lower grid and distributor plate; (2) damage to lower internal grid, distributor plate, etc.; and (3) if outer end fitting can be easily removed. o Blocked flow holes probed. 08/30/85

RPE, REV. 3 APPENDIX C Page 2 of 8 6-386 - Lower CSA Defueling Method Selection - Based on lower CSA inspection and debris analysis, necessary tooling development and procurement will be identified. 7-381 - Lower CSA Tooling: Engineer, Deliver, Install, and Test - The tools selected in Block 6-386 will be designed, procured, and tested. Following successful demonstration, the tools will be installed in the RB. 8-386 - Upper CSA Exam - Video inspections of the upper CSA will be performed by inserting a fiber optic scope through the core former plate flow holes. These inspections combined with previous video camera examinations will assist in the determination of (1) fuel accumulation on the core lower plates and internal areas of the CSA, (2) potential damage to the CSA structure and core lower plates / walls, and (3) debris concentrations and structural distortion of exposed surfaces. 9-384 - Lower Head Properties / Sample Analysis - Video and sample material taken in the lower head examinations (reference Block 12-384) will be analyzed for. radionuclide content, maximum temperature, and composition. 10-386 - Lower Head Defueling Method Selection - Based on data from Lower Head Properties / Sample Analysis (reference Block 9-386), a method for defueling will be selected. 11-381 - Lower Head Tooling: Engineer, Deliver, Install, and Test - Tooling required for the defueling method selected will be designed, procured, and tested. Tool operators will be trained. 12-384 - Lower Head Exam - Video inspection of the elliptical flow distributor and incore guide tubes will be performed (where possible). This activity will also include retrieval of liquid 1 and solid material samples. j 08/30/85 e

RPE, REV. 3 APPENDIX C Page 3 of 8 13-386 - Lower Head Verify Integrity - Prior to core boring operations (reference Block 19-386), which precede lower vessel defueling activities, RV integrity must be verified. This task will establish the method for verifying RV integrity. Current considerations are (1) internal video inspection, (2) video external. inspection, and/or (3) ultrasonic testing of in-core nozzle welds and lower head exterior. B&W has prepared an analytical study of lower head integrity based on current data. 14-384 - Lower Head Debris Relocation - Debris in the lower head will be relocated (this may be accomplished by vacuuming to the core region) to determine if vacuming is a reasonable method of defueling and if large solid masses are present. 15-386 - Early Defueling Operations - Based on the core region defueling strategy (reference Block z3-384), early defueling operations encompass the following activities: o Loading canister and debris baskets without significant debris size reduction o Transferring debris basket loads to canisters - o Relocating debris in preparation for vacuuming operations o Vacuuming o Transferring loaded canisters out of the reactor vessel. 16-384 - Decision Regarding Core Boring - A decision will be made to i determine if the core boring equipment developed by DOE will be i used to extract several undisturbed, full-length core samples for accident analysis. The number and location of samples are to be determined. 17-311 - Core Boring Operation - Assuming that the decision in Block 16-384 is to proceed, cut core samples, load samples into fuel canisters, and transfer out of the reactor vessel. 18-386 - Bulk Defueling Operations - Bulk defueling will include, in addition to the operations described in early defueling operations (reference block 15-386), size reduction and the use i of special tools to complete core defueling.

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RPE, REV. 3 APPENDIX C Page 4 of 8 19-386 - Lower CSA Defueling Operations - Lower CSA defueling operations will remove core debris from the CSA~ below the lower grid including cutting and removal of structural materials for access to remove fused debris. ' Some debris may be moved to the RV bottom head. 20-384 - Decision to Bypass Lower Head - Based on infomation on RV integrity, a decision will be made to address or bypass lower head defueling at this time. 21-386 - Lower Head Defueling Operations - Lower head defueling operations will include pick and place, vacuuming, and size reduction operations. Care will be exercised to limit loads on in-core instrumentation nozzles. 22-386 - Upper CSA Defueling Operations - Flushing and vacuuming methods are planned for defueling debris bearing areas of the upper CSA. Cutting of the baffle plates and core barrel along with removal of vent valves' may be required for access. 23-384 - Core Region Defueling Strategy - This procedure establishes controlling steps and provides instructions for accomplishing RV defueling. 24-387 - Pump 18: Remove Components and Motor - Remove reactor coolant pump motor, decontaminate, and locate in storage area. 25-387 - Pum) 18: Prepare Area for Defueling - If the RV water level is to >e maintained at the bulk defueling level, one option would be to procure, fabricate, install, and test a leaktight container which would be mounted on the reactor coolant pump and to install a work platform and video system. Following this, the pump internals will be removed, defueled, decontaminated, and stored. Preparations may vary from those described above depending on defueling method decisions. 26-387 - Pump 18: Defuel Discharge Piping - This task includes vacuuming and mechanical scraping of discharge piping to remove fuel debri s. 27-387 - Pump 18: Defuel J-Leg - This task includes vacuuming and pick and place operations to defuel the J-leg. 08/30/85

RPE, REY. 3 APPENDIX C Page 5 of 8 28-387 - Pump 1B: Defuel Bottom Heat Once-Through Steam Generator (OTSG) - Select defueling method. One of the methods under consideration is vacuuming supplemented by robotic applications. 29-384 - Core Region Exam - Multiple video inspections of the core region will be perfomed to inspect the crust layer beneath the loose debris bed. Examinations will specifically address hardness and size of the crust layer. The region below the crust will also be examined. Current plans are for a minimum of three examinations: (1) after plenum removal and before defueling; (2) after vacuuming and before bulk defueling; and (3) after bulk defueling; and, as needed, throughout defueling. 30-387 "B" D-Ring Dose Reduction - Defueling will begin in the "A" D-ring followed by the "B" D-ring. Dose reduction activities will be prioritized to support the defueling schedule. They will include dose reduction work to allow D-ring access for mechanical and hydraulic defueling activities. 31-387 - Defuel "B" 0TSG Upper Tube Sheet - This activity encompasses defueling method selection and implementation. Current plans include: o Prepare area for defueling by removing manhole covers and installing shielding o Install video system o Remove fuel and debris by " pick and place" and wet vacuuming methods. 32-387 - Remove "B" D-Ring Components for Pump Access - This activity includes removing: o Items stored in D-ring o Support hangers, support beams, and rods that support pump motors o Piping o Pipe hanger-steel, platforming, electrical cable and conduit o Reactor coolant pump rigid restraints and earthquake snubbers In addition to the above, staging and storage areas must be identified for removed components. Components to be removed from the RB will need to be decontaminated. 08/30/85 ~

RPE, REV. 3 / APPENDIX C Page 6 of 8 33-387 - Pump 28: Remove Components and Motor - See block 24-387. 34-387 - Pump 28: Prepare Area for Defueling - See block 25-387. 35-387 - Pump 28: Defuel Discharge Piping - See block 26-387. 36-387 - Pump 28: Defuel J-Leg - See block 27-387. 37-387 - Pump 28: Defuel Bottom Head OTSG - See block 28-387. 38-387 - D-Ring Access - Implement dose reduction activities in both D-rings to support ex-vessel fuel characterization activities. 39-387 - Ex-Vessel Fuel Location Operations "A" D-Ring - Radiation surveys will be performed to locate and quantify fuel within the RCS system in the "A" D-ring. Specific survey locations follow: o Pressurizer o Reactor Coolant Pumps o OTSG o Core Flood Line o J-legs 40-387 - Ex-Vessel Fuel Removal Plan - This issued technical plan presents information pertaining to mechanical, hydraulic, and chemical methods for removing fuel and debris; and the applicability of mechanical and hydraulic methods to each of the identified potential ex-vessel fuel bearing locations. 41-381 - Ex-Vessel Fuel Removal Tools: Engineer, Deliver, Install, and Test - An engineering evaluation will be performed to select tooling for ex-vessel fuel removal. Once selected, tooling will be designed, fabricated, tested, and installed. 42-387 - Defuel Decay Heat Drop Line - A method to defuel the decay heat drop line will be selected and then implemented. Current planning includes flushing debris to the RV and vacuuming into canisters. 43-387 - Defuel Core Flood Tank Lines - A method to defuel the core flood tank line will be selected and implemented. One method currently being evaluated is to fill the core flood tank with borated water, apply nitrogen over pressure, and flush debris to the RV for vacuuming into canisters. 08/30/85

RPE, REV. 3 APPENDIX C Page 7 of 8 44-386 - Lower Head Final Defuel and Cleanup - Implement " pick and place" and vacuuming operation in the lower head while protecting -in-core instrument nozzles. 45-386 - End Point Verification - Methods will be selected at the completion of the defueling operation to verify that the program completion criteria have been met. Verification will likely include examination, surveys, and sample collection and analysis. 46-387 - Ex-Vessel Fuel Location Operations "B" D-Ring - Similar to operations described in block 39-35/. Specific survey locations are the OSTG, J-legs, RCPs, and dec4y heat drop line. 47-387 - Pump 1A: Remove Components and Motor - See block 24-387. 48-387 - Pump 1 A: Prepare Area for Defueling - See block 25-387. 49-387 - Pump 1A: Defuel Discharge Piping - See block 26-387. 50-387 - Pump 1A: Defuel J-Legs - See block 27-387. 51-387 Pump 1A: Defuel Bottom Head OTSG - See block 28-387. 52-386 - Defueling End Point - Defines defueling end point criteria which are practical, capable of being verified, and consistent with program and regulatory objectives that will be developed. 53-381 - End Point Planning / Engineering - This task develops techniques and equipment for completion verification including equipment manufacture and test. This task also includes planning and scheduling verification activities. 54-387 "A" D-Ring Dose Reduction - See block 30-387. 55-387 - Defuel "A" OTSG Upper Tube Sheet - See block 31-387. 56-387 - Defuel Pressurizer Bottom Head - This task is comprised of the development and implementation of a defueling plan for the pressurizer bottom head. Preparations include spraying down the pressurizer internals, gaining access, and installing video systems. Operations would be accomplished with long-handled i tools and vacuum system with a vacuum line routed through the surge line to the RV vacuum equipment. l 08/30/85 l

RPE, REY. 3 APPENDIX C Page 8 of 8 57-387 - Defuel Surge Line - The plan is to flush debris to the RV. 58-387 - Remove "A" D-Ring Components for Pump Access - See block 32-387. 59-387 - Pump 2A: Remove Components and Motor - See block 24-387. 60-387 - Pump 2A: Prepare Area for Defueling - See block 25-387 61-387 - Pump 2A: Defuel Discharge Piping - See block 26-387 62-387 - Pump 2A: Defuel J-leg - See block 27-387. 63-387 - Pump 2A: Defuel Bottom Head OTSG - See block 28-387. 08/30/85 w -

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APPENDIX D TMI-2 RECOVERY PROGRAM ESTIMATE REVISIDN 3 DECONTAMINATIDN AND DOSE REDUCTION ACTIVITY

SUMMARY

Drawings D-1 through D-4 summarize planned decontamination and dose reduction activity logic and workscope through program completion in 1988. They identify activities required to accomplish program objectives as well as alternative activities that may be required should chemical i decontamination be necessary. Costs for activitiesfin support of chemical decontamination are excluded from this estimate. The following paragraphs, cross referenced to specific activity boxes on 1 Drawings D-1 through D-4, briefly describe the nature of the identified activi ties. Block reference numbers appear first followed by WBS l 4 {

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i The four logic diagrams are as follows: D Auxiliary / Fuel Handling Bldg Decon and Dose Reduction D Reactor Building Decon and Dose Reduction l D Non-RCS Systems Decon and Dose Reduction l l D Reactor Coolant System Decontamination 4 D Auxiliary and Fuel Handling Building Decontamination and Dose Reduction Activity Logic Diagram l 101-235 - Maintenance Decontamination - Maintenance decontamination is an ongoin!) task to the end of Phase III to maintain a desired leve' of radiological cleanliness after completion criteria have been achieved. 102-235 - Technical Specification Decontamination - Certain inspections of equipment and facilities as required by Technical Specification require access to currently inaccessible areas of the AFHB. To improve radiological conditions there is an ongoing effort to reduce radiation dose rates and to decontaminate these areas to levels which permit personnel entry. i -31 08/30/85

RPE, REV. 3 APPENDIX D Page 2 of 13 103-236 - Auxiliary and Fuel Handling Building Decontamination Technical Plan - This technical plan establishes the objectives for decontamination and radiation levels for the cubicles and general areas of the AFHB. It also establishes the priorities for the decontamination of these cubicles. 104-241 - Completion Criteria Technical Plan - This technical plan will estaDitsn tne Pnase III objectives for radiological conditions and fuel remaining in plant systems. 105-231 - Radiological Characterization - Characterization of general area dose rates, hot spots, and surface contamination levels is necessary to support cubicle surfaces and non-RCS system decontamination. 106-236 - Cubicle Surface Decontamination - The AFHB Decontamination Technial Plan establishes the surface contamination objectives for cubicles in the AFHB. 107-236 - Modify Spent Resin Storage Tank (SRST) - The spent resin storage tank will be modified to receive and process contaminated sludges from both the reactor building and the AFHB. This task will require significant engir.eering and labor man-hours. 108-236 - Install Sludge Transfer System - The sludge transfer system will be a temporary piping systcm installed to transfer sludges from several areas in the AFHB and reactor building. This task is being done in conjunction with the modification of the spent resin storage tank. 109-236 - Desludge Miscellaneous Waste Holdup Tank (MWHT) - The miscellaneous waste holdup tank is currently scheduled to be the first tank or sump to be desludged using the sludge transfer system and the spent resin storage tank. 110-236 - Desludge Other AFHB Sumps and Tanks - After the sludge nandling equipment is demonstrated to be operational, the remaining sumps and tanks in the AFHB can be desludged. The sequence in which these operations will be performed is currently undetermined. 209-227 - Desludge RB Basement - See explanation under Drawing 0-2. 1 08/30/85

i RPE, REV. 3 APPENDIX 0 i Page 3 of 13 h 111-236 - AFHB Resin Transfer - The sludge handling system will process the ion exchange resin contained in the domineralizers of the AFHB. Resins from such sources as the makeup and purification domineralizer will be collected in the spent resin storage tank for processing. 112-End of Phase III - Attainment of cleanup program ' radiological conditions. D-2 Reactor Building Decontamination and Dose Reduction Activity logic Diagram 201-245 - Identify Tasks Requiring Robots - Identify tasks in the 4 reactor Du11 ding requiring tne use of robots due to high radiation levels in the basement. 202-245 - Robotics Development - Robots will be used for a variety of tasks ranging from characterization and data acquisition tasks to decontamination and dose reduction activities such as scabbling and hydrolazing. Robotics development will continue throughout most of the basement recovery activities. 203-221 - Reactor Building Basement Characterization - Reactor building basement characterization activities such as sludge sampling, concrete core boring, and radiological surveys will be ongoing throughout the basement recovery. These tasks will be perfomed primarily by robots and are dependent on timely robotics development. 204-227 - Reactor Building Basement Strategy Technical Plan - The Reactor Building Basement Strategy Plan is complete and was issued in December 1984. This technical plan establishes the basement recovery program objectives and provides the technical guidance required to achieve them. 205-227 - Reactor Building Basement Decontamination Technical Plan - Ints technical plan w111 provide tecnnical guidance with regard to the activities required to achieve decontamination and dose reduction completion criteria in the basement. i 08/30/85

RPE, REV. 3 APPENDIX D Page 4 of 13 206-227 - Reactor Building Basement Recovery - The Reactor Building Basement Strategy Plan outlines the scope of this program; i.e., the basement recovery effort will be achieved by stabilizing one zone at a time. These efforts will require extensive removal of highly contaminated concrete and concrete blocks, primarily by robots. Extensive data acquisition will be required to support tasks in the basement. 104-241 - Completion Criteria Technical Plan - This technical plan will include all of the radiological end points for the reactor building and will be used to guide the planning of all activities in the building. The building completion criteria published in the Completion Criteria Technical Plan will be derived primarily from the Reactor Butiding Decontamination and Reactor Building Basement Strate Technical Plans. (Reference Drawing D-1, block 104-24 207-227 - Resolve Reactor Building Basement Criticality Concerns - To ensure that an inadvertent criticality will not occur during reactor building basement sludge transfer operations, a safety evaluation will be perfonned. 208-227 - Reactor Building Sludge Transfer Skid - To transfer the sludge from the floor, a special sludge transfer skid will be fabricated and installed. A robot will be used to move sludge from the floor and transfer it to the skid. Pumps on the transfer skid will then pump the sludge from the RB basement to the spent resin storage tank in the AFHB. 209-227 Desludge Reactor Building Basement - The sludge on the basement floor and in the basement sump will be transferred to the s)ent resin storage tank in separate operations as the ro)ot gains access to the various zones in the basement. It will not be a single operation but a series of individual operations using the sludge transfer skid. Sludge in the RB sump will be transferred using sump pumps for transfer to the spent resin storage tank. The order in which floor and sump transfers will be perfonned is currently undefined. 08/30/85

r l l RPE, REY. 3 APPENDIX 0 i Page 5 of 13 t l 210-227 - Reactor Building Decontamination Technical Plan - The Reactor Building Decontamination Technical Plan will provide the Phase III end points for the RB above the 305' elevation. It will also provide specific direction regarding the sequence in which areas in the building are i decontaminated to Phase III completion criteria. 211-227 - Estabitsh HVAC Controls in the Reactor Building - The Reactor Building Technical Plan calls for the establishment of HVAC controls to aid in the prevention i of recontamination of previously decontaminated areas and l the transport of contamination throughout the building in general. Techniques such as vent filtering and air flow l balancing and control will be used to achieve these goals. 212-227 - Decontaminate Reactor Building 347' Elevation and Above - l The Reactor Building Decontamination Technical Plan l states that Phase III decontamination will begin with the reactor building dome and proceed down to the lower areas of the building. The technical plan delineates six zones on the 347 elevation and above and states that zones l should be decontaminated in sequence from one to six. i 213-227 - Establish Contamination Isolation from Other Plant Areas - During the decontamination of the zones l identified in the Reactor Building Decontamination Technical Plan, it will be necessary to prevent cross contamination between the zone being worked in and the zones adjacent to it. 214-227 Decontaminate Reactor Building 305' Elevation and Above - XTter the 347' elevation and areas above have been decontaminated, the remaining areas outside of the D-rings on and above the 305' elevation will be decontaminated. The Reactor Building Decontamination Technical Plan identifies four zones in this region. Decontamination on the 305' elevation should begin in zone seven and proceed in order to zone ten. 215-227 - Decontaminate D-Rings on the 305' Elevation and Above - The last areas above the basement to be decontaminatt'd will be the "A" and "B" D-rings. The "A" D-ring will be decontaminated first followed by the "B" D-ring. These decontamination activities will take place at or above i the 305' elevation. The basement level of the D-rings will be handled as part of the overall basement recovery program. 08/30/85

- - - ~ - RPE, REV. 3 i APPENDIX D l Page 6 of 13 t L 216-227 - Defueling Manres Reevaluation - The defueling manrem i reevaluation will predict the man-hours to be spent in i various areas of t w reactor. building and take into l account the radiation levels in these areas. Dose reduction efforts will be directed to problem areas providing the highest ALARA benefit. l 217-225 - Reactor Building Dose Reduction Technical Plan - This l technical plan presents the overall reactor building dose i i reduction strategy and provides guidance for dose l l reduction work to provide an ALARA radiological l environment for reactor disassembly and defueling. 1 1 218-225 - Reactor Vessel Defueling Dose Reduction - These activities w111 center primarily around dose reduction on the 305' and 347' elevations of the building and support l Phase II defueling operations by reducing personnel radiation exposure. 219-387 - Ex-Vessel Defueling Dose Reduction - It may be necessary l l to aeruel regions of tne RW outsfde Of the reactor i vessel; i.e., the pressurizer, reactor coolant pumps, and steam generators contained in the D-rings. It will be necessary to reduce the radiation levels in tne "A" and '"B" D-rings in order to reduce the exposure to personnel l participating in the ex-vessel defueling effort. l l l 220 386 - Reactor Vessel Defueling - While reactor vessel defueling is not itself a part of the decontamination and dose l reduction program, the logic diagram illustrates how such a program relates to defueling. 221-387 - Ex-Vessel Defueling - As with reactor vessel defueling l above, ex-vessel defueling is not itself a part of the l i decontamination and dose reduction program. The logic diagram illustrates how such a program relates to l l defueling. T f ) 417-243 - RCS Decontamination onerations - In order to achieve Phase III radiologica' conditions in the reactor building, it may be necessary to decontaminate the RCS. RCS decontamination is the subject of the Reactor Coolant System Decontamination and Dose Reduction Logic Sequence Diagram and therefore will not be' discussed Iwre. It is shown on the reactor building logic diagram only to illustrate how this work fits into the scheme of reactor (Reference Drawing D-4, block building) activities. { 417-243. 08/30/85 i

RPE, REV. 3 APPENDIX D Page 7 of 13 222-225 - Reactor Building Maintenance Decontamination - The reactor building is a highly contaminated environment. It will be necessary to continue a program of maintenance decontamination throughout the recovery effort. D-3 Non-RCS Systems Decontamination and Dose Reduction Activity Logic Diagram This estimate provides for flushing, draining, and sealing of non-RCS systems. Mechanical or chemical methods of decontamination of non-RCS systems are not included in this estimate. 301-241 - Ex-RCS Criticality Safety Technical Plan - This technical plan establishes criticality sarety guidelines for the decontamination of ex-RCS systems. The plan was published in November 1984 and is currently being revised. The criticality safety issues discussed in the plan relate to the following non-RCS systems: o Makeup and Purification o Waste Disposal Miscellaneous Liquids o Waste Disposal Reactor Coolant o Waste Disposal Reactor Coolant Leakage Recovery o Decay Heat Removal. 302-241 - Non-RCS Systems Fuel Characterization - The Ex-RCS Criticality Safety Technical Plan requires characterization of the systems to detennine their fuel content. The technical plan establishes the technique for system characterization as gamma spectroscopy keyed on Ce-144, 303-243/- Non-RCS Systems Decontamination Technical Plan - This 244 technical plan establishes progransnatic guidance for the decontamination of non-RCS systems at THI-2. It provides for the flushing and draining of those systems suspected of containing fissile material or systems having radiation dose rates above the limits for the areas in the AFHB or RB. 104-241 - Completion Criteria Technical Plan - This technical plan will establish the Phase III objectives for radiological conditions and fuel remaining in plant systems. It establishes the general area and how to spot dose rates \\ l 08/30/85 l

RPE, REV. 3 l APPENDIX D Page 8 of 13 104-241 - Completion Criteria Technical Plan - (cont'd.) for areas in the AFH8 and RB. This criteria will be used to detemine whether a system needs to be decontaminated. (Reference Drawing D-1, block 104-241.) 304-244 - Select Pumps for Use in Systems Decontamination - To flush and drain contamina3ed systems, Site Engineering has identified pumps for use in systems decontamination operations. These pumps are on site and can be placed in service as required. 305-244 - AFH8 Decontamination Technical Plan Cubicle Priority List - The AFHB Decontamination Technical Plan establishes the sequence and priority in which cubicles are to be decontaminated. Th'is cubicle listing also drives the selection and prioritization of systems flow paths to be decontaminated. 306-244 - Start AFHB System Decontamination Flowpath Selection - site t.ngineering is currently coing tne engineering for decontamination of approximately a dozen specific flowpaths in the AFHB. These flowpaths were selected to-reduce dose rates in the top priority cubicles identified in the AFHB Decontamination Technical Plan. 307-244 - Pump ECAs and Installation - Site Engineering has selected a set of pumps to be hard piped to take suction from a fixed water source and deliver it to the systems being decontaminated. Engineering Change Authorizations need to be prepared and the pumps installed. 308-241 - Systems Radiological Characterization - A systems characterization program is required to develop a comprehensive set of data on systems radiological conditions to determine what piping systems contribute to the general area and hot spot dose rates. 309-244 - Select Other Decontaminatten Flowpaths - The remaining systemt flowpaths requiring decontamination will be identified and prioritized as sufficient radiological characterization data are available. 310-244 - Flowpath Selection and Ensineering - Once a particular flowpath has been selectec for decontamination, the engineering and operations software (ECAs, DTSs, UWis, etc.) must be prepared to accomplish the decontamination operations.

08/30/85

RPE, REV. 3 APPENDIX D Page 9 of 13 311-244 - Procure / Install Ecluipment - The majority of flowpaths will probably be cecontaminated using existing or procured equipment. This equipment will have been identified as part of the engineering effort. 312-244 - Decontamination Operations - Decontamination operations will usually consist of flush and drain operations. However, it may be necessary to use more aggressive chemical or mechanical decontamination techniques to achieve Phase III completion criteria. These aggressive techniques will require more engineering effort and more specialized equipment than standard flush and drain operations. Decontamination operations will be primarily the responsibility of Recovery and Site Operations. This task will be repeated for every flowpath requiring decontamination. 313-241 - Receive and Evaluate Solvent Qualification Report from Pacific Nuclear Systems (PNS) - A series of solvent evaluation tests have been performed on contaminated TMI-2 artifacts. Results of these tests will provide the basis for selecting the solvents that can be used in systems decontamination. 314-241 - Select Solvent Evaluation Laboratory - It may be necessary to do additional solvent qualification work after receiving the PNS report. If required, a solvent evaluation vendor will be selected who has a background in chemical decontamination technology as well as adequate laboratory facilities. 315-241 - Obtain Contaminated Plant Samples - If further chemical solvent qualification testing is needed, contaminated plant samples must be obtained for use in testing. 316-241 - Complete Solvent Qualification Program - Af ter the solvent qualification vendor has received the contaminated THI-2 samples, they can complete the solvent qualification program. At this point, all of the research and development work on solvent processes l will be complete. ! 08/30/85 l i

t l RPE, REV. 3 APPENDIX D Page 10 of 13 l 317-241 - Prepare Chemical Decontamination Planning Study - A planning study will be prepared to evaluate the results l l of the solvent qualification activity. The planning study will review the decontamination effectiveness and j waste treatability of each solvent tested. 318-241 - Prepare Chemical Decontamination Technical Plan - A Chemical Decontamination Technical Plan will recommend specific chemical solvent processes that can be used at TMI-2. This technical plan will identify solvents for use on specific systems. It will also describe waste treatment processes compatible with exisiting TMI-2 equipment. D-4 Reactor Coolant System (RCS) Decontamination and Dose Reduction Activity Logic Diagram This estimate provides for flushing, draining, and sealing of the RCS, Mechanical or chemical methods of decontamination of the RCS are not included in this estimate. 104-241 - Completion Criteria Technical Plan - This technical plan w111 De issued in August Iven. It will establish the Phase III objectives for many areas of concern such as radiological conditions and fuel remaining in plant systems. The Completion Criteria Technical Plan will establish the Phase !!! completion criteria for radiological conditions in the reactor building including radiation dose rates in the vicinity of the RCS. (Reference Drawing D-1, block 104-241.) 210-227 - Reactor Building Decontamination Technical Plan - The Reactor Building Decontamination Technical Plan will provide the Phase !!! completion criteria for all of the reactor building above the 305' elevation. These completion criteria will be the basis for the Completion Criteria Technical Plan. In addition, the plan will establish specific directions regarding the sequence in which various areas in the building (are decontaminated to Phase !!! completion criteria. Reference Drawing 0-2, block 210-243.) 08/30/85

l RPE, REV. 3 APPENDIX D Page 11 of 13 401-243 - Estimate Post-Defueling Dose Rates - To predict the need to decontaminate the RCS, calculations of radiation levels due to various levels of internal system surface l contamination will be performed. A model of the RCS is being created to predict the contribution of RCS contamination to general area dose rates. As more information becomes available on RCS internal l contamination, it will be added to the data base to refine the estimates of RCS dose rate contribution. 402-243 - RCS Decontamination Planning Study - This planning study will evaluate technologies available for RCS decontamination in order to choose which method or methods should be used to achieve Phase III completion criteria. An estimate of post-defueling dose rates will be presented in this planning study. 403-243 - RCS Decontamination Technical Plan - This technical plan will determine the techniques to be used and the scope of work to be performed to decontaminate the RCS. 404-241 - Select Solvent Evaluator - If preliminary post-defueling dose rate estimates indicate a strong probability that it will be necessary to decontaminate the RCS, it may be beneficial to begin evaluation of chemical decontamination solvents that could be used in the RCS. i The first step in such a solvent qualification program is the selection of a solvent evaluation vendor. 405-241 - Take RCS Samples and Test - To develop and select the optimum solvent, contaminated RCS specimens will be used as sample coupons in solvent testing. 406-241 Solvent Qualification and Selection - The objective of this work is to select a solvent that can be used at THI-2. Such a solvent must be capable of both meeting the desired radiological end points as well as being capable of undergoing waste processing at reasonable cost. 407-241 - Select Mechanical Decontamination Techniques Evaluator - If preliminary post-defueling dose rate estimates indicate a strong probability that it will be necessary I to decontaminate the RCS, it may be beneficial to begin limited research and development of mechanical 08/30/85 i

F l RPE, REV. 3 APPENDIX D Page 12 of 13 407-241 - Select Mechanical Decontamination Techniques Evaluator - (cont'd.) decontamination techniques that could be used to decontaminate the TM1-2 RCS. The first step in such research and development is the selection of a vendor to perfom the required evaluation program. 408-241 - Take RCS Samples and Test - To develop and select the cost useful mechanical decontamination techniques, it will be necessary to acquire contaminated RCS specimens that can be used as sample coupons in testing. 409-243 - Mechanical Technique Development and Selection - Once Ine mecnanicai tecnniques evaluator nas received the necessary RCS samples, he may test the samples using a variety of mechanical methods. The objective of this work will be to select mechanical decontamination techniques which can be used at TMI-2. 410-241 - RCS Film Characterization - To predict post-defueling dose rates as well as to select the best available technology for decontaminating the RCS it will be necessary to characterize the radiological and physical nature of films deposited on RCS internal surfaces. Radiological data will be used to predict system-wide post-defueling dose rates while chemical and hardness testing will be used in selecting the optimum decontamination technique. 411-241 - RCS Radiological Characterization - As defueling progresses, the radiological data collected in the vicinity of the RCS will be the most useful infomation used in evaluating the need to decontaminate the RCS. While calculated post-defueling dose rates will give an early indication of the need to decontaminate the RCS, the final decision will be based on survey data. 412-243 - Evaluate the Requirement for Vendor Services - If the decision is made to decontaminate the RCS, evaluate the use of on site resources or vendor services to accomplish the RCS decontamination. 08/30/85

l l RPE REV. 3 l APPENDIX D Page 13 of 13 l l 413-243 - Evaluate RCS Closure and Access Points - Before a final decision is made on the method used to decontaminate the RCS, the ability to seal the system must be evaluated. Chemical decontamination of the RCS will probably require the system be sealed, whereas mechanical decontamination methods probably will not. 414-243 - Engineering / Design - Prepare engineering and operations software required to plan, schedule, and monitor the decontamination activities, and procure equipment or vendor services. 415-243 - Acquire Equipment / Vendor - Acquire any special equipment or vendor services to perform kCS decontamination. 416-243 - Equipment Installation and Testing - Install and test the required equipment and provide training. 417-243 - RCS Decontamination Operations - RCS decontamination operations will be completed at the same time as or after defueling operations and will be scheduled based on logistics requirement; i.e., availability of resources and access to work areas, j 220-386 - RV Defueling - Reference Drawing 0-2, block 220-386. 220-387 - Ex-Vessel Defueling - Reference Drawing D-2, block 220-387. l i 08/30/85

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APPENDIX E TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 LEVEL-4 WBS COST DETAIL ($ x 1000) 1985-1988 WBS PROGRAM SUPPORT 1985 1986 1987 1988 Total Site Management 1880 1600 1350 450 5280 Recovery Programs 7010 5000 3800 2800 18610 Site Operations 3325 2920 2830 1370 10445 Technical Planning 1105 81 0 550 200 2665 Licensing & Nuclear Safety 3300 3300 2100 800 9500 Gov't & Industry Programs 970 970 600 2540 Other Divisions /G&A 33780 33540 26460 18160 111940 TOTAL WBS-1 51370 48140 37690 23780 160980 WBS STABILIZATION, DEGONTAMINATION AND DOSE REDUCTION WBS 1985 1986 1987 1988 Total RB Characterization 221 Total 220 1320 550 20 2110 Recovery Programs 1200 500 20 1720 Technical Planning 220 120 50 390 08/30/85

RPE, REV. 3 APPENDIX E Page 2 of 7 W8S STABILIZATION, DECONTAMINATION AND DOSE m.uucitun (cont'a.J WBS 1985 1986 1987 1988 Total RB Dose Reduction 225 Total 560 1680 800 300 3340 Recovery Programs 480 1600 800 300 3180 Technical Planning 80 80 160 RB Decon 227 Total 15 5000 11500 7300 23815 Recovery Programs 15 5000 11500 7300 23815 AFHB Characterization 231 Total 65 805 750 1620-Recovery Programs 700 700 1400 Technical Planning 65 105 50 220 AFHB Dose Reduction 235 Total 2370 3570 2400 600 8940 Recovery Programs 2275 3500 2400 600 8775 Site Operations 30 30 Technical Planning 65 70 135 AFHB Decon - 236 Total 400 3100 4900 1800 10200 Recovery Programs 400 3100 4900 1800 10200 Systems Characterization ~ 241 Total 140 1540 1075 2755 Recovery Programs 1300 1000 2300 Technical Planning 140 240 75 455 R8 Systems Decontamination 243 Total 65 1880 2025 4300 8270 Recovery Programs 1800 2000 4300 8100 Technical Planning 65 80 25 170 AFHB Systems Decontamination 244 Total 3080 4000 1800 8880 Recovery Programs 3000 4000 1800 8800 Technical Planning 80 80 Robotics 245 Total 1030 1030 Recovery Programs - 1030 1030 08/30/85

RPE, REY. 3 APPENDIX E Page 3 of 7 WBS STABILIZATION, DECONTAMINATION AND DOSE MLDUGIIDN (cont'd.) WBS 1985 1986 1987 1988 Total Additional Scope 2XX Total 4000 8800 12800 Recovery Programs 3800 8800 12600 Site Operations 200 200 Total - Recovery Programs 4200 21200 31600 24920 81920 ( Total - Site Operations 30 200 230 Total - Technical Planning 635 775 200 1610 I TOTAL WBS-2 4865 21975 32000 24920 ~83760 l l l l WBS REACTOR DISASSEMBLY AND DEFUELING WBS 1985 1986 1987 1988 Total DOE Data Acquisition 311 Total 1145 900 200 2245 Recovery Programs 935 700 200 1835 Site Operations 40 40 l Technical Planning 170 200 370 RD&O Related Modifications 32X Total 9180 9180 Recovery Programs 9180 9180 I Reactor Head Lift & Store 353 Total 300 300 Recovery Programs 300 300 Plenum Operations 373 Total 1630 300 1930 Recovery Programs 1585 300 1885 l Site Operations 10 10 l Technical Planning 35 35 ) i i

08/30/85 i

l E

RPE, REY. 3 APPENDIX E Page 4 of 7 WBS REACTOR DISASSEMBLY AND DEFUELING (cont'd.) WBS 1985 1986 1987 1988 Total Defueling Tooling 381 Total 11580 3800 2300 17680 Recovery Programs 11580 3800 2300 17680 Canisters 382 Total 6100 2000 550 8650 Recovery Programs 6100 2000 550 8650 Racks 383 Total 745 745 Recovery Programs 745 745 Defueling Preparations 384 Total 3725 3725 Recovery Programs 3010 3010 Site Operations 130 130 Technical Planning 585 585 In-Vessel' Fuel Removal 386 Total 7835 7000 4755 400 19990 Recovery Programs 6985 4800 2690 400 14875 Site Operations 670 2200 2065 4935 Technical Planning 180 180 Ex-Vessel Fuel Removal 387 Total 875 8825 2020 11720 Recovery Programs 31 0 8310 1200 9820 Site Operations 240 820 1060 Technical Planning 565 275 840 Core Accountability 388 Total 50 25 400 475 Recovery Programs 30 30 Site Operations 200 -200 Technical Planning 20 25 200 245 CSA Defueling 39X Total 170 675 2400 3245 Recovery Programs 5 51 0 - 2300 2815 Technical Planning 165 165 100 430

08/30/85 J,_.

RPE, REV. 3 APPENDIX E Page 5 of 7 WBS REACTOR DISASSEMBLY AND DEFUELING (cont'd.) WBS 1985 1986 1987 1988 Total Additional Scope 3XX Total 5000 5000 Recovery Programs 5000 5000 Total - Recovery Programs 40465 20120 14240 1000 75825 Total - Site Operations 850 2440 3085 6375 Total' - Technical Planning 1720 665 300 2685 TOTAL WBS-3 43035 23225 17625 1000 84885 WBS RADI0 ACTIVE WASTE MANAGEMENT WBS 1985 1986 1987 1988 Total Solid Radwaste Processing 421 Total 1765 1605 1605 800 .5775 Recovery Programs 1585 1600 1600 800 5585 Site Operations 175 175 Technical Planning 5 5 5 15 Solid Radwaste Packaging 422 Total 800 800 A00 2000 Recovery \\ Programs 800 800 400 2000 Solid Radwaste Shipping 424 Total 1910 2230 3755 1500 9395 Site Operations 1910 2230 3755 1500 9395 Solid Radwaste Facilities 425 Total 1720 1985 350 300 4355 Recovery Programs 1640 1900 300 300 4140 Technical Planning 80 85 50 215 Large Component Disposal 426 Total 2300 1150 3450 Recovery Programs 1300 1300 Site Operations 1000 1150 2150 08/30/85

RPE, REV. 3 APPENDIX E Page 6 of 7 WBS RADI0 ACTIVE WASTE MANAGEMENT (cont'd.) WBS 1985 1986 1987 1988 Total Liquid Radwaste Processing 431 Total 2035 3090 2285 ~ 6410 13820 Site Operations 1885 2920 2190 6410 13405 Technical Planning 150 170 95 415 -Fuel Material Disposal 442 Total 1160-4790 4305 2105 12360 Recovery Programs 1075 1500 2575 Site Operations 3200 4255 2105 9560 Technical Planning 65 90 50 225 Additional Scope 4XX Total 7850 4350 12200 Recovery Operations 2400 2400 Site Operations 5450 4350 9800 Total - Recovery Programs 4300 5800 6400 1500 18000 Total - Site Operations 3970 8350- 16650 15515 44485 Total - Technical Planning 320 350 200 870 TOTAL WBS-4 8590 14500 23250 17015 63355 WBS GENERAL RECOVERY FACILITIE5/5YSTEMS WBS 1985 1986 1987 1988 Total Containment Air Control Envelope 511 Total 270 270 Recovery Programs 270 270 Radiation / Air Monitoring Systems 543 Total 1500 1500 3000 Recovery Programs 1500 1500 3000 Ground-water Monitoring 545 Total 500 500 1000 Recovery Programs 500 500 1000 TOTAL WBS-5 270 2000 2000 4270 08/30/85

RPE, REV. 3 APPENDIX E Page 7 of 7 WBS PLANT STABILITY / SAFETY WBS 1985 1985 1987 1988 Total Hazardous Waste Control 621 Total 630 520 465 360 1975 Site Operations 630 520 465 360 - 1975 Equipment Operation 622 Total 2510 2015 1455 940 6920 Recovery Programs 105 105 Site Operations 2405 2015 1455 940 6815 TMI-2 Chemistry 623 Total 1115 1105 605 275 3100 Site Operations 1115 1105 605 275 3100 Operations Maintenance 631 Total 6705 6690 5565 3810 22770 Recovery Programs 2850 3500 3000 2000 11350 Site Operations 3635 3090 2515 1810 11050 Techni. cal Planning 220 100 50 370 Maintenance Planning' 632 Total 430 395 275 175 1275 Site Operations 430 395 275 175 1275 Operations Engineering 641 Total 855 995 520 215 2585 Site Operations 855 995 520 21 5 2585 Radiochemical Engineering 643 Total 355 430 150 935 Site Operations 355 430 150 935 Additional Scope 6XX Total 1700 1700 3400 Site Operations 1700 1700 3400 Total - Recovery Programs 2955 3500 3000 2000 11455 Total - Site Operations 9425 8550 7685 5475 31135 Total - Technical Planning 220 100 50 370 l TOTAL WBS-6 12600 12150 10735 7475 42960 08/30/85

l APPENDIX F TMI-2 RECOVERY PROGRAM ESTIMATE i REVISION 3 POTENTIAL UNPLANNED WORKSCOPE (5 x 1000) Reference Related l Number WBS Element Basis for Exposure 1 1 00 Program Support - Phase III end point completion criteria have not been fully. 200 defi ned. Achievement of an acceptable end point could' require greater work effort 400 than currently planned. j 600 2 1 00 Program Support - General social / regulatory / political / fiscal considerations could affect schedule and cost; e.g., broad-based labor problems (strike), licensing delays (court injunctions, protracted public hearings), or political interference. 1 3 100' Program Support - Premium costs associated with schedule maintenance. j i 4 227 RB Decentamination - Basement decontamination has been estimated on the basis of currently envisioned robotic devices and limited characterization. Actual conditions may require additional equipment. l 5 227 & RB and AFHB Decontamination - RB and AFHB systems decontamination is based on ~ water i 236 flush and dry layup. If chemical decontamination is required, costs for chemical flushes and equipment must be added. 6 387 Ex-Vessel Fuel Removal - Estimate is based on being able to remove ex-vessel fuel by vacuuming and through identified access points. Need for extraordinary equipment such 1 as robotics or chemical dissolution of fuel could increase costs and extend schedule. l 1 i 08/30/85

o RPE, REY.3 APPENDIX F Page 2 of 2 i j Reference Related Number WBS Element Basis for Exposure i 7 424 Solid Radwaste Disposal - Disposal of plant processed water as solid waste. 8 425 Solid Radwaste Systems - Waste shipping and disposal costs are based on low specific activity (LSA) disposal at Hanford, Washington through 1988 and no storage on site thereafter. Construction and operation of an on-site low-level radwaste storage facility would increase program costs. i 9 442 Fuel Shipping - The DOE fuel shipping agreement includes a specific period of perfonnance. Program schedule delays could negatively affect the ability to meet j contract fuel shipping schedules and result in additional cost. E 10 600 Plant Stability / Safety - Plant stability / safety costs are based on a 10CFR50 license i ] conversion occurring at the completion of fuel removal. Allowance for delays in securing the planned license change, or a more restrictive license, was not included 4 in the estimate. TOTAL ALLOWANCE FOR UNPLANNED WORKSCOPE -- $33.4MM i I l 08/30/85 I,

4 APPENDIX G TMI-2 RECOVERY PROGRAM ESTIMATE REVISION 3 PROGRAM STAFFING PLAN (I) TOTAL BY TMI-2 DIVISION ORGANIZATION 1985 1986 1987 198B(2) Total TOTAL BY YEAR - 1015 1055 930 570 3570 Office of the Director 4 4 3 2 13 Program Controls 25, 18 16 7 66 Recovery Programs 620 700 675 473 2468 Site Operations 274 258 1 91 75 798 Technical Planning 43 26 11 2 82 Licensing & Nuclear Safety 39 39 28 11 117 Government & Industry 10 10 6 0 26 Programs PERSONNEL DISTRIBUTION 1985 1986 1987 1988(2) Total TMI-2 DIVISION 1015 1055 930 570 3570 Nonmanual 588~ 397 304 207 1496 Manual 427 657 626 363 2073 SYSTEM 329 31 4 252 129 1024 Nonmanual 142 137 111 59 449 Manual 187 177 141 70 575 CONTRACTOR 686 741 678 441 2546 Nonmanual 446 261 193 148 1048 Manual 240 480 485 293 1498 (1) Totals exclude Support Divisions' personnel (2). Average number of personnel required for a 9-month period. , 08/30/85

~ APPENDIX H TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 TMI-2 PROJECTED WASTE GENERATION

SUMMARY

.a,b

---

Comme rc i al D i s po s al ----------------

Total ......... Class........ U.S. . Year Volume A B C DAW

• Liners DOE T971 20567 YBT67 1980 26841 20423 6418 1981 14890 9360 5530 50 1982 6379 6229 150 828 1983 17009 12339 4670 1818 1984 9512 7982 1530 5262 4250 42 1985 17167 16717 225 225 14667 2500 58 1986 21388 19388 1000 1000 16978 4410 60 1987 17848 16198 825 825 14978 2870 100 1988 16733 16233 350 150 13833 2900 20 TOTAL 168334 76518 3930 2200 134636 33698 2976 b NOTES:

.a - Volumes in cubic feet b - Excludes fuel to DOE; 1985-88 are best estimates

REFERENCES:

GPU Nuclear Corporation Memorandum, dated April 25, 1985;

1. 4520-85-0032; from C. P. Deltete to S. Levin, " Revised Waste Projections 1985-1990" GPU Nuclear Corporation Memorandum, dated June 27, 1985;
2. 4520-85-0054; from C. G. Hitz to S. Levin, " Revised Abnormal Waste Projections"

• Dry Activated Waste 08/30/85 4

REFERENCES TMI-2 REC 0VERY PROGRAM ESTIMATE REVISION 3 1. GPU Nuclear Corporation, August 1984. TMI-2 Defueling Study. 2. GPU Nuclear Corporation, November 1984. Work Breakdown Structure, Technical Plan, TP0/TMI-116. 3. GPU Nuclear Corporation, July 1985. TMI-2 Program Strategy, Technical Plan, TP0/D11-115, Draft. 4. U.S. Department of Energy, March 15, 1982. Memorandum of Understanding Between the U.S. Nuclear Regulatory Commission and the U. S. Department of Energy Concerning the Removal and Disposition of Solid Nuclear Wastes from Cleanup of the Three Mile Island Unit 2 Nuclear Plant. 5. GPU Nuclear Corporation, March 1985. Auxiliary and Fuel Handling Building Decontamination, Technical Plan, TP0/TMI-130, 6. GPU Nuclear Corporation, August 1985. TMI-2 Core Accountability, Technical Plan, TP0/TMI-035. 7. General Public Utilities Corporation, August 1,1980. TMI-2 Recovery Program Estimate. 8. Metropolitan Edison Company, July 1981. TMI-2 Recovery Program Estimate, Rev.1. 9. GPU Nuclear Corporation, December 30, 1982. TMI-2 Recovery Program Estimate, Rev. 2.

10. GPU Nuclear Corporation Memorandum from C. P. Deltete, April 25, 1985, Revised Waste Projections 1985-1990, to S. Levin,

1. 4520-85-0032.

11. GPU Nuclear Corporation Memorandum from C. G. Hitz, June 27, 1985, Revised Abnormal Waste Projections, to S. Levin, #4520-85-0054 08/30/85 1}}