ML20009H455
| ML20009H455 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/03/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-043, CON-NRC-TMI-81-43 NUDOCS 8108100133 | |
| Download: ML20009H455 (6) | |
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weewo DISTRIBUTION TMI Program Office /HQ r/f TMISITE r/f August 3) 1981
.etfTRAL FILE NRC/THI-81-043 NRC PDR LOCAL PDR Site Operations file HEMORANDUM FOR:
Harold R. Denton, Director Office of. Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FROM:
Lake H. Ba'rrett, Deputy Program Director TMI Program Office
SUBJECT:
NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of July 26 - August 1,1981.
ORIGINAL SIGNED BY:
Lake H. Barrett Deputy Program Director THI Program Office
Enclosure:
As stated cc: E00 OGC Office Directors Commissioner's Technical Assistants mi NRR Division Directors 1 dh to NRR A/D's N'
Regional Directcrs
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t'RC TMI PROGRAM OfflCE HEEKLY STATUS REPORT Week of July 26 - August 1,1981
_ Plant Status Core Cooling Mode lleat trans fer from the reactor coolant system (RCS) l loops to Reactor Building ambient.
Available Core Cooling Modes:
Decay heat removal systems.
Long term cooling "B" (once through steam generator-B)
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Modes: Mini Decay lleat Removal (H0llR) System.
Decay lleat Removal (DilR) System.
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Major Parameters (as o'f 0500, JuIy 31,1981) (approximate values)
Average Incore Thermocouples: 120*F i
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Maximum Incore Thermocouple:
143*F l
RCS Loop Temperatures:
A B
110t Leg 119 F 122 F
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Cold leg (1) 73*F 75 F (2) 74*F 75*F RCS Pressure:
95 psig Reactor Building:
Temperature:
76 F Water level:
Elevation 290.9 ft. (8.4 ft, from floor) via panetration 401 manometer Pressure:
-0.44 psig Concentration:
4.6 x 10-6 (LLD) uCi/ml Kr-85 (Sample taken 7/23/81)
Efluent and Environmental (Radiological) Information 1.
Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period July 24, 1981, through July 30, 1981, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources which originated within Unit 2 contained no detectable radioactivity.
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Environmental Protection Agency '(EPA) Environmental Data.
Results from EPA monitoring of tne environment around the IMI site were as follows:
3 The EPA measured Kr-85 concentrations (pci/m ) at several environmental monitoring stations and reported the following resul ts :
Location _
July 3 - July 17,1981 3
(pCi/m )
Golds boro 21 Observation Center 27 Middletown 22 Yorkhaven 26 m.,
s s
All of the above levels of Kr-85 are considered to be back-ground levels'.
No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gamma ~ rate networks during the period from July 23, l#81, through July 30, 1981.
3.
NRC Environmental Data.
Results from NRC monitoring of the environ-ment around the IMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-1 31 Cs-137 Sample Period _
(uCi/cc)
(uct/cc)
HP-278 July 22,1981 - July 30,1981
<8.0 E-14 <8.0 E-14 4
Licensee Radioactive _ Material and Radwaste Shipments.
On Monday, July _ 27,1981, a 40 ml Unit 2 reactor coolant
'j sample was sent to Babcock ~and Wilcox (B&W), Lynchburg,--
On Tuesday, July 28, 1981, 21 drums of Unit 1 compacted and solidified LSA waste were shipped to Chem-Nuclear System, Incorporated, Barnwell, South Carolina.
On Wednesday, July 29, 1981, 42 drums and 8 metal boxes, containing Unit 1 compacted and noncompacted LSA waste and I Unit 2 dewatered preaccident resin liner were shipped to Chem-Nuclear System, Incorporated, Barnwell, Soutii Carolina.
On Thursday, July 30, 1981, 81 drums containing Unit 1 and Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries, Utica, New York.
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r Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of the second tia~tch (approximately 50,000 gallons)~ of intermediate radioactivity water from the Auxiliary Building Reactor Coolant Bleed Tank (RCBT) was completed on July 31, 1981.. Processing was interrupted a
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number of times because of operational problems and once because a leak developed from a gasket on a processed water storage tank.
The leak was minor (approximately 1 pint of water leaked to the soil) and since the leak did not directly interfere with SDS operations, processing was resumed to another tank while the leak was repaired.
Preliminary results indicate that the total curie loading after completion of. the second processing batch is approximately 680 curies of Cs-137 and 340 curies of Sr-90 on the first ion exchange vessel.
This loading represents greater than 99% removal of. these radioactive
.. f third b'a'tch (appro,ximately)50,000. gallons)g of RCB materials from the process st. ream.
Stagin was completed over the weekend (August 1-August 2 and processing of this water started
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August 2, 1981.
2.
Reactor Buildino Entry.
The. fifteenth entry into the Unit 2 Reactor Building has been scheduled for August 27, 1981.
The licensee has
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tentatively proposed
- the following tasks for the fifteenth ent'ry:
Closed circui~t TV maintenance Reposition refueling bridge and survey deep end of refueling pool Survey Reactor Building interior with gamma spectrometer Survey of air coolers Barrier installation around elevation 305' floor hatch and placement of rubber mat over high beta field -
Miscellaneous clean up work and tool removal Overhead smear survey, elevation 305' '
Floor smears, elevation 305' Instrument remov'al for accident effects studies Survey of Reactar Building sump refill pipe path Reset radiation area monitor alann Video tape potential hose paths for Reactor Building decontamination f
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Reactor Building sump sample near drain tank rupture disk discharge The above list of tasks is still under review by the licensee and the tiRC'onsite staff.
3.
itemorandum of Understanding Between UStiRC_ and. US Department of Energy _.
A Memorandum of7nderstanding has been signed between the US 11uclear Regulatory Coninission (flRC) and the US Department of Energy (DOE) concerning the removal and disposition of solid nuclear wastes from cleanup of the Three Mile Island Unit 2 fluclear Plant.
Dated July 15, 1981 the agreement specifies' interagency procedures to help ensure that the TMI site does not become a long-term waste disposal facility.
Close ' cooperation)e't' ween thh two agencies is cipected to ensure 7,
the following disposition of THI-2 accident generated solid radio-active wastes which currently exist or are planned to be generated:
EPICOR-II system wastes - forty-nine liners are on site with loadings up to 1500 curies.
DOE is. developing a high int.egrity container which may allow disposal in existing licensed commercial land burial facilities (1-2 years from now).
Alternately, DOE may elect to take the liners for a research and development program for waste analysis and processing, or take possession on a reimbursable basis.for storage or disposal.
Submerged Demineralizer System wastes - DOE will take possession and retain, for research and development purposes, zeolite liners used for disposition of accident generated radioactive matericls.
Reactor fuel - DOE will analyze appropriate samples, with the remains being stored in containe'rs in the TMI-2 spent fuel i
storage pool.
Disposition of the balance of the damaged fuel 1
will await resolution of the generic spent fuel storage issue.
Transuranic contaminated waste materials '- waste materials accumulated, at TMI with transuranic levels above the acceptance criteria at conrnercial land burial facilities will be considered on a case-by-case basis by DOE.
Al~ternatives include archiving, research and development, temporary onsite storage or DOE processing / disposal with reimbursement by the licensee.
Makeup and pur.ification system resins and filters - due to the-
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high levels of contamination deposited on these filters from
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the accident and the generic value of analysis, DOE will take possession and retain these filters for research and development activities, or for storage and disposal on a reimbursable basis.
Any part of the memorandum of understanding may be modified with the agreement of both parties.
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-S-Future Meetinos 1.
On ~ Thurscay, August 6,1981, Lake Barrett will meet with area mothers to discuss various issues related to the decontamination-of THI Unit 2.
2.
.On Tuesday, September 1,1981, the Citizens Advisory Panel for the Decontamination of TMI Unit 2, will meet from,7:00 p.m. to 10:00 p.m.
at the lloliday Inn, 23 South Second Street in liarrisburg, to discuss current activities at TMI.
This meeting will be open for public observation.
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