ML20199D514
| ML20199D514 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/16/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-057, CON-NRC-TMI-86-57 NUDOCS 8606200363 | |
| Download: ML20199D514 (4) | |
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June 16, 1985 NRC/THI-86-057 1
HE110RANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation m
Frank J. Miraglia, Director c
Division of PWR Licensing-B 7
FROM:
William D. Travers, Director TMI-2 Cleanup Project Directorate d
9
SUBJECT:
JRc M '> CLEA5ilP-PROJECT DIRECTORATE WEEKLY STATUS 5
REPORT FOR JUNE 9 - JUNE 15,1986 E
1.
DEFUELING The drilling rig for core stratification has been disassembled and is being prepared for installation in the reactor building later y
this week. Core boring is scheduled to start on June 26, 1986.
Pick and place defueling activities continued. These activities were conducted to clear core bore drilling locations and for training and testing of the heavy duty tong tool and heavy duty hydraulic impact chisel. The number of canisters transferred to the fuel pool remains at 42.
The Reactor Coolant System (RCS) turbidity was variable, depending p
on defueling operations, but typically with 1 - 2 feet of visibility.
One of the internals vent valves was removed. This will allow x
improved access to the lowr reactor vessel head region for testing of the vacuum defueling system in that area. The removal of
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additional vent valves is scheduled for this week.
1-2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to the t
atmosphere. Core cooling is by natural heat loss to ambient 2
building atmosphere. The average incore thermocouple reading is 79'F; reactor vessel water temperature as measured by resistance temperature detectors (RTD's) is 74 F.
The airborne radioactivity on the defueling platform is about 3 E-7 uC1/cc Tritium and 4 E-10 uC1/cc particulates, predominately j
Cesium-137 and Strentium-90. The platform is mounted above the modified internals indexing fixture which is mounted over the m
8606200363 860616 PDR ADOCK 05000320 R
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NRC FORM SIS 00-80) NRCM 0240 OFFICIAL RECORD COPY
Harold R. Denton 2
June 16, 1986 Frank J. Hiraglia NRC/THI-86-057 reactor vessel. These provide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.
3.
WASTE MANAGEMENT The Submerged Denineralizer System (SDS) is processing batch S-133.
SOS processing to date has been 3,995,991 gallons.
EPICOR II is processing batch 290 and 291. Tne system has processed 2,958,534 gallons to date.
4.
ENVIRONf! ENTAL 110NITORING US Environnental Protection Agency (EPA) sample analysis results show that Tl!I site liquid effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.
The Lancaster water sample taken at the ; tater works river intake and analyzed by EPA consisted of a seven day composite sample taken May 25 - 31, 1986. A gamma scan detected no reactor related activity.
TMI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from May 25 - 31, 1986. A gamma scan detected no reactor related activity.
The EPA analysis of the NRC outdoor air sample for the period June 6
- 13, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system, i.e.,
less than 1.1 E-13 microcuries/cc.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES A fuel canister CD-(38) is in the west upender in spent fuel pool "A".
The canister is slightly tilted which will not allow normal
'rappling. GPUN personnel are investigating the cause and preparing g
to take corrective actions.
Asseably of the Desludging system continued.
The testing program continues on the transfer shield, cask upender, and other components needed to support fuel shipping.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Canister liandling and Preparation for Shipment Safety Evaluation l
Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Core Stratification Sample Safety Evaluation Report, Revision 4.
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unc e nu sia nosoi nscu o2" OFFICIAL RECORD COPY
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y Harold R. Denton 3
June 16, 1986 C<
' Frank J. Miraglia NRC/THI-36-057 b
c 7.
PUBLIC ftEETING t
The Advisory Panel for the Decontamination of THI-2 met with the NRC Commissioners in Washington, D.C. on June 11, 1986. At that meeting, the following items were discussed:
9 ilh 1)
The Panel expressed satisfaction with the recent ACRS review of the issue of potential recriticality during THI-2 defueling.
2)
The Panel requested a briefing on the April 14, 1986 cleanup
,J schedule revision submitted by GPUH. Dr. W. Travers, Director of the NRC's THI Cleanup Project Directorate provided the staff's prelinicary assessment of the. reasons for the revised schedule.
3)
The Panel informed the Comission of the continuing interest and yf/c,
concern of the local citizens regarding THI-2 health issues.
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Neb 4)
The Panel reported on a recent presentation by the Department of Energy (DOE) regarding off-site shipment of the damaged Ti!I-2 fuel.
5)
The Commission and the Panel discussed proposed Panel activities for 7;
the near future and also addressed the question of.the point at which Panel activities will conclude.
W 6)
The Panel reiterated its concern over the delay in resolution of the y
polar crane enforcement action.
7)
The Panel requested timely receipt of major cleanup documents Y
anticipated to be submitted in the next few months.
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.The next meeting of the Advisory Panel will be held at a date and I
-location to be detennined.
L C/UGW7. M Mr L'
y;m D. tr.:m1 William D. Travers Director THI-2 Cleanup Project Directorate 4
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wnc ranu ais tiosai nneu ano OFFICIAL. RECORD COPY
Harold R. Denton 4
June 16, 1986 Frank J. Miraglia flRC/T!!I-86-057 INTERNAL DISTRIBUTION CEliTRAL FILE flRC PDR LOCAL PDR EDO OGC Cffice Directors Comissioner's Technical Assistants NRR Division Directors liRR A/D's Regional Administrators IE Division Directors TAS EIS PilS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI THI HQ r/f Till SITE r/f THI-2 Project Section File TIII Cleanup Project Directorate (10) c 4
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