ML20154R069
| ML20154R069 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/24/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-027, CON-NRC-TMI-86-27 NUDOCS 8603280036 | |
| Download: ML20154R069 (4) | |
Text
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March 24, 1936 NRC/TMI-36-027 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nucl?ar Reactor Regulatior.
Frank J. Miraglia, Director Division of PWR Licensing-B J
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William D. Travers Director THI-2 Cleanup Project Directorate
SUBJECT:
NRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MARCH 17 - MARCH 23, 1986 1.
DEFUELING As of March 23, 1986, 28 debris canisters have been transferred from the reactor vessel to pre-shipmnt storage. These cans have a total net weight of 30,678 lbs. which is about 10% of the estimated core material originally in the reactor vessel.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to anblent building atmosphere. The incore thermocouple average is 80"F.
The airborne radioactivity on the defueling platform is about 7.1 E-7 uCi/cc Tritium and 3.0 E-11 uti/cc particulates, predominately Cesium-137. The platfons is mounted above the modified internals indexing fixture which is mounted on the reactor vessel flange.
These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.
3.
WASTE MANAGEMENT g.
The Submerged Demineralizer Systen (SDS) continued processing batch 130 from the "C" Reactur Coolant Bleed Tank (RCBT) to the monitor tanks then to the "A" RCBT.
SDS total processed to date is 3,842,869 gallons.
EPICOR II was in temporary shutdown this week. EPICOR II total processed to date is 2,854,371.
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4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show Till site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge (includes THI-1 and TMI-2) to the river consisted of seven daily composite sanples taken from !! arch 1 through March 3,1986. A gama scan detected no reactor related activity.
These EPA samples are then sent to Pennsylvania - Department of Environmental Resources (PA-DER) for detemination of Tritium, gross Alpha emitters and gross beta emitters. These data are normally available about two months from sampling. Unit l's resuned operation is accompanied by normal releases of fission and activation products, which are allowed by Technical Specifications.
Tritium is the only isotope released in detectable quantities. The average concentrations reported in the THI-1 Effluent Summary for October - December 1985 (244 pCi/1, 330 pC1/1, 1700 pC1/1) were consistent with the PA-DER Tritiun values as detected in 20 of 92 daily outfall samples. These Tritium values are much less than 1/1,000 of the limit of 3,000,000 pCi/1.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from March 2 through itarch 8,1986. A gama scan detected no reactor related radioactivity. No Tritium was detected during October - Decemoer 1985 The NRC outdoor airborne particulate sampler at the THI site collected a sample between March 13, and 20,1986. No reacter related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 cnneentrations to be less than the lower limits of detectability.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of Defueling Water Cleanup System (0WCS) continued.
The Kelly vacuuming decontamination in the 281' elevation of the fuel handling building has resulted in the release of 75% of the general access areas from loose contanination controls.
The initial Seal Injection Valve Room (281' Auxiliary Building) entries on March 17 and 21 were judged to be successful in removing boron which built up on rubber and lead shielding installed in 1930-1981. The low pressure water flush proved the floor drain is opera ting.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
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! N AC FORM 318 H0 30) NRCM 0240 OFFICIAL. RECORD COW j
1, Harold R. Denton 3
x Harch 24, 1986 Frank J. fliraglia NRC/THI 86-027 Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
THI-2 Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 1.
7.
PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for April 10, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.
Persons desiring the opportunity to speak before the Advisory Panel are asked to contact Mr. Thomas Snithg111 at 717-291-1042 cr write to him at 2122 Itarietta Avenue, Lancaster, PA 17603.
OmoINAE SK M D BY Ynmas D. T overs Willian D. Travers Director THI-2 Cleanup Project Directorate
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