ML20235L812
| ML20235L812 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/28/1987 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-87-074, CON-NRC-TMI-87-74 NUDOCS 8710050607 | |
| Download: ML20235L812 (5) | |
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1 7
September 28, 1987 NRC/TMI-87-074 l
MEMORANDUM FOR:
Dennis M. Crutchfield, Director Division of Reactor Projects - III. IV,V & Special Projects l
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Frank Schroeder, Jr., Assistant Director Region IV Reactors and Special Projects FROM:
William D. Travers, Director l
v THI-2 Cleanup Project Directorate l
SUBJECT:
NRC THI-2 CLEANUP PROJECT DIRECTORATE STATUS I
REPORT FOR AUGUST 31 - SEPTEMBER 28, 1987
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I 1.
DEFUELING Pick and place defueling of the core region continued. Part length fuel assemblies constitute the bulk cf the work effort and mass of material removed with 125 of 177 assemblies having been loaded into 3
defueling canisters.
Some fuel pins are loose or splayed within a partial length assembly. These are cut and loaded individually.
Additionally some agglomerated, once molten material called " rocks" is usually loaded separately but occasionally attached to partial assemblics.
Currently, approximately 160,000 lbs out of a total of approximately 300,000 lbs of core debris and other materials has beer loaded. The total mass to be removed includes the mass of the core, 207,000 lbs; structural and absorber materials 78,000 lbs; and mass added by oxidation of core and structural material 8,500 lbs. Additionally, portions of the baffle plates, formers, and other components may become comingled with core debris during cutting operations. An estimate of 6,500 lbs was used for this material to bring the total to 300,000 1bs.
Completion of removal of partial length fuel assemblies is expected in December of this year. This will complete defueling of the core region.
The next two areas to be defueled are the lower internals and the lower head (below the noral core region). The lower internals is the region between the lower grid top rib section and the elliptical flow distributor head. This area contains a mixture of loose material and solidified, once molten material in the spaces between the horizontal structural components and in the flow holes of the structural components.
The bulk of the material in this area is likely to be solidified, once molten material. The lower head is the her.fspherical bottom of the reactor vessel and also contains a 8710050607 870928 arm =>
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September 28, 1987 A
Frank Schroeder, Jr.
NRC/TMI-87-074 l
mixture of loose material and solidified once molten material.
The bulk of the n. ass in this area is likely to be luose and vacuumable.
Defueling of the areas between the baffle plates (radially outside the normal core region) und the core barrel will follow.
The decay heat drop line has a significant quantity of fuel and will probably be defueled with the remainder of the reactor coolant system piping.
Ex-vessel detueling activities are now concentrated on defueling of the "B" steam genera tur. Datueling of the pres.;urizer and initiation of defueling activities in the reactor coolant system decay heat drop leg.are also expected before the end of the current year.
3.
ENVIRONMENTAL NONITORING US Environmental Protection Agency (EPA) sample analysis results show tnat TMl site liquid effluents are in accordance with regulatory limits. NRC requirements, and the City of tencaster Agreeraen t.
Till water effluents from the station (Units 1 and 2) discharge are analyzed by EPA.
Ganana spectrum ent. lyses of the daily composited Sdmples for August 15 through September 12, 1987 indicated na reactor related activity.
EPA's gama spectrum analysis of the NRC's TM1 cutdocr air suples for August 28 - September 4, September 4 - 11, September 11 - 18, dnd September 18 - 25, 1987 showed no reactor related radioactivity.
The water works for the City of Lancaster composited seven daily samples from August 16 - 22, August 23 - 29, August 30 - September 5, and September 6 - 12, 1987.
EPA's gamma spectrum analysis of the composite samples showed no reactor related radioactivity.
4.
DECONTAMINATION ACTIVITIES During August 1987. Phase 111 endpoints were reached for six areas.;
The areas were the nitrogen gas header, the reactor coolant evaporator room, the area and sump below the main steam relief valves (M-20 area) in the service building, the external piping area for the borated water storage tank, and the east corridor of the fuel handling builuing 328' elevation.
The sludge removed fra the reactor building basement floor was salid.fied in two disposal liners.
The liners ware transferred to the onsite tunparary storage fadlity to awoit shipment to an offsite shallow land afsposal facility.
Resins removed from the reactor coolant cleanup demineralizers were soliditied and moved to the tmporary si;orage facility for later shipment to u buriel site.
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~' Dennis H. Crutchfield 3
Septesber 28, 1987
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l Frank Schrreder, Jro ffRC/THI-87-074 Preparations are being made to move the makeup and purification deminerali:er resin to a consolidation tank for sampling prior to solidification. These resins will be stabilized in concrete and temporarily stored prior to transport to a burial site.
The "A" Once-Through-Steam-Generator (OTSG) upper tube sheet was cleaned of debris by pick-and-place end vacuuming.
Pick-and-place yielded about 5 pounds of rock / gravel debris while vacuuming produced about 5 pounds of finer debris.
On September 8,1987 the licensee staff briefed the THICPD staf f on the status of their decontamination and radiation level reduction program and their plans for further activities in this area.
Further progress has been made in all major areas of decontamination. The auxiliary building sump and reactor building sludge removal has been completed and the reactor building gross flush is in progress. Seventy-five percent of the previously contaminated areas (462,708 sq.ft.) of the auxiliary and fuel handling buildings'have been decontaminated to Phase III levels, 11 systems tlushes out of 22 planned have been accomplished, 2 of 10 tenks desludged and 7 of 9 demineralizers cleaned._ Of 143 ccataminated cubicles, 107 have been decontaminated to Phase III levels, leaving 36 to decontaminate.
Twenty-three of the remaining 36 are scheduled for decontaminatica in 1987.
Projected cumulative worker dose for 1987 (1027 person-rem)isbelow the licensee's goal of 1175 person-rem and just 120 person-rem (13%)
dbove the 907 person-rem total for 1986. The major contributor to the aversion of doses during 1987 is the reduced dose rates on the shielded defueling work platform.
The results of a licensee study of the various options for decontaminating the reactor building basement are expected shortly.
Such options span the range from leaving the basement virtually as is to utilizing mechanical and chemical means to physically remove the contaminated material.
Leach tests are still in progress es a basis for determining the fasibility of removing radioactivity from the reactor building basement by flooding part or all of it follcsed by processing of the water to remove the radioactivity. The results of these tests will be considered in en upcoming report.
4.
.t,(RC EVALUATIONS IN PROGRESS Technical Specification Change Requests 52, 53 and S6.
Recovery Operations Plan Change Request 30.
Solid Haste Facility Technical Evaluation Report.
Processed Water Disposition Proposal.
Pressurizer Defueling Safety Evaluatica Report.
Safety Evaluation Report for Defueling of the Cure Support Assembly.
Environmental Evaluation of the Post-Defueling Hanitored Storage Proposal.
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4 September 28, 1987
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Frank Schroeder, Jr.
NRC/TMI-87-0/4
.1 Canister Handling and Preparation for Shipment Safety Evaluation Report, Revision 4 and Revision 5.
f Defueling tiater Cleanup System Technical Evaluation Report Annual Update.
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Defueling Canister Technical Evaluation Report Annual Update.
EPICOR II System Description Annual Update.
Request for Exeroption from 10 CFR 70.42 Requirements.
Staging of Lirers in the t'aste Handling and Packaging Facility.
During the reparting period, the NRC staff approved the licensee's proposed organization plan changes 16 and 17.
These changes involved a realignment of divisional responsibilities at the corporate level and minor changes in the defueling organization at the TNI-2 site.
In addition, the staff completed a. preliminary review of Technical Specification Change Request 53.
This change involves a realignment of the Technical Specification requirements in preparation for a phased entry to the Post-Defueling Honitored Storage period. The staff has forwarded comients to the licensee and has requested additional information to support the licensee's proposal.
A review of the environ-r. ental impacts of the licensee's Post-Defueling Monitored Storage prograra is in progress with a draf t supplement to the PElS tentatively scheduled for issuance in January 1938.
5.
PUBLIC MEETIkG No date has been set for the next w eting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2.
The details of the next meeting will be announced, OaptW.
p D. Tr*'"5 William D. Travers Director TMI-2 Cleanup Project Directorate OF F ICE )
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September 28, 1987 3
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