ML20205R323
| ML20205R323 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/30/1987 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-87-029, CON-NRC-TMI-87-29 NUDOCS 8704060311 | |
| Download: ML20205R323 (4) | |
Text
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m March 30, 1987 NRC/TMI-87-029 J
MEMORANDUM FOR:
Harold R. Denton, Director Office of fiuclear Reactor Regulation Frank J. Miraglia, Director Division of PWR Licensing-B FROM:
William D. Travers, Director TMI-2 Cleanup Project Directorate
SUBJECT:
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MARCH 23 - 29, 1987 1.
DEFUELING Attempts to remove additional partial-length fuel assemblies using the hydraulic cam clamp tool and the pole snare were unsuccessful.
Defueling teams cut fuel pins at the core drilling test pattern area and partially loaded two fuel canisters using the heavy duty spade bucket.
2.
ENVIRONMENTAL M0llITORING US Environn: ental Protection Agency (EPA) sample analysis results show that TBI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
Tiil water effluents are sampled from the station (Units 1 and 2) discharge end analyzed by EPA. Ganca spectrum analyses of the seven daily ceraposited samples for March 7 - 14, 1987 indicated no TMI-2 related radicactivity.
EPA's gamma spectrum analysis of the NRC's THI outdoor air sample for the period March 19 - 27, 1987 showed no reactor related radioactivity. The EPA laboratory's lower level of detection for fodine-131 and cesium-137 is about 6 E-14 uCi/cc.
The water wcrks for the City of Lancaster composited seven daily samples from March 8 - 14, 1987. The gamma spcctrum analysis for the composited sample performed by EPA shcwed no reactor related radioactivity.
3.
DECCNTAMINATION ACTIVITIES Scabbling of the ficar beneath the B and C bleed tanks continued.
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Desludging' of the auxiliary building sump continued.
Final preparations are being made to pump sludge from the reactor building basement to ide auxiliary building.
4.
NRC EVALUATI0f;S a.
Completed Revision 2 to the Sediment Transfer and Processing Safety Evaluation Report was approved on March 26, 1987.
Coagulant Criticality Safety Evaluation Report was approved on March 27, 1987.
b.
In Progress Technical Specification Change Request numbers 49 and 51 and the associated Recovery Operations Plan Change Requests 31 and 33.
Technical Specification Change Requests 52, 55 and 56.
Solid Waste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Frocessed Water Disposition Proposal.
Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 3.
Pressurizer Defueling Safety Evaluation Report.
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Safety Evaluation Report for Defueling of the' Core Support Assembly.
Seismic Evaluation for l',cdified Containment Penetration.
5.
MEETING On the evening of March 25, 1987, the Advisory Panel for the Decentamination of Three Mile Island Unit 2 held a public meeting at the Holiday Inn, Harrisburg, PA. At this meeting the Panel received presentations on the issue of Accident-Generated Water Disposal from Drs.
R. Piccioni and E. Sternglass. Statements from Drs. M. Kaku and C.
Johnson were read at the meeting by members of the Susquchanna Valley Alliance. The Panel also received a number of public coments on the licensee's proposal for the disposal of accident-generated water.
The Panel voted 8 - 2 finding the fiRC staff's draft supplen.ent to the PEIS an acceptable evaluation of alternatives and enviraraental impact.
The Panel voted 5 - 4, with one abstention to not endorse the licensee's proposed evaporation option for water disposal. The Panel also voted 10 - O against any discharge of the water to the Susquehanna River.
The next ceeting of the Advisory Panel is scheduled for April 16, 1987 in Washington, DC, before the i.RC Comissioners. The neeting will be open to the public and will address processed accident-generated water disposal.
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