ML20132F061
| ML20132F061 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 07/08/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-047, CON-NRC-TMI-85-47 NUDOCS 8507180245 | |
| Download: ML20132F061 (3) | |
Text
- - _ - _
ms F
July 8, 1985 NRC/TIII-85-047 HEHORANDUll FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder Program Director THI Program Office FROH:
William D. Travers, Deputy Program Director THI Program Office
SUBJECT:
NRC THI PROGRNi 0FFICE WEEKLY STATUS REPORT FOR JULY 1, 1985 - JULY 7, 1985 x
1.
PLAlli STATUS
. 1
);
The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed.
The reactor vessel plenum has been removed from the reactor vessel and placed on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between t1e deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a The modified internals (indexing fixture is installed on the reactor depth of about 20 feet about 5 feet above the top of the plenum).
vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor butiding ambient atmosphere.
Incore themocouple readings range fron 73'F to 94*F with an average of 83*F. Average cold leg temperature is 58'F.
The average reactor building temperature is 63*F. The reactor building airborne activity is 7.4 E-9 uCi/cc tritium, and 2.7 E-10 8
uC1/cc particulate, predominantly cesium 137.
2.
WASTE MANAGEMENT Doth the Submerged Domineralizer System (SDS) and EPICOR II were shutdown during this period.
Total volume processed through SDS to date is 2,898,836 gallons,and the total volume processed through EPICOR !! is 2.480,774 gallons.
3.
00$E P.EDUCTI0ft/DEC0liTAMINATI0ft ACTIVITIES Shielding of the reactor building air coolers is in progress.
Aveinge general area radiation dose rate is 36 mrem por h c
347' level of the reactor building and is 160 mren per hour on the
/
305' level of the reactor building.
l
,/j p
,f
~**
g7100245050700 ADOCM 05 coo 3go su "** *
...............R-pon
..""{~~....
i
" " " ~ ~ " ~
C3 P@a000000Ma cmp 0240 ONICI AL RECORD COPY
}
f.
Harold R. Denton 2
July 8, 1985 g,
Bernard J. Snyder NRC/THI-85-047 y.
h 4.
ENVIRONMENTAL HONITORING
- +
EPA sample analysis results show THI site liquid effluents to be in accordance with regulatory limits,!!RC requirements, and the City of Lancaster Agreement.
TMI water samples taken by the US Environmental Protection Agency at M
the plant discharge to the river consisted of seven daily composite samples taken from June 15, to June 22, 1985. Gamma scans detected no reactor related radioactivity.
The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consisted of a 5 ;f seven day composite sample taken from June 16, to June 22, 1985. A ganena scan detected no reactor related radioactivity.
7 The NRC outdoor airborne particulate sampler at the T!!! Site collected a sample between June 27, and July 3, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
u
!M 5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES
,y 9
Installation of the DWCS continued. Partial DWCS turnover for M
processing RCS during early defueling is scheduled to be completed i
in late August.
6.
NRC EVALUATIONS IN PROGRESS Defueling W)ater Cleanup System Technical Evaluation (including Revision 6 Technical Specification Change Requests numbers 46, 48, and 50 Equipment Hatch Renoval Safety Evaluation Recovery Operations Plan Change numbers 27, 29. and 32
'Fuci Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program Defueling Safety Evaluation 7.
PROJECTED SCHEDULE OF FUTURE EVENTS Start of Defueling:
September 1985 8.
PUBLIC HEETING The next meeting of the Advisory Panel is scheduled for 7:00 PH, July 18,1985, at the Public Service Building, 201 North Duke Street, Lancaster, PA.
l'
/
p sono sy, w omem D. Teevees x
William D. Travers Deputy Program Director T'!! %gm 0"5
- = " >............
o "*" >............
OFFICIAL RECORD COPY
- wne rg;u ais oo so Nncu ano
Harold R Denton 3
July 8, 1985 Bernard J. Snyder flRC/Till-85-047 IflTERllAL DISTRIBilTIO:4 EDO OGC Office Directors Commissioner's Technical Assistants llRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS Till Program Office Staff (10)
PilS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI T!!IPO liq r/f Till SITE r/f CEllTRAL FILE NRC POR LOCAL POR Till-2 Project Section File
)
=a"^= >.d.HI5%...
'$.Ml.2P.h '.
5,2. ' E....... T.4.
o"'a >.T T
h des..
cow 9t 1... T4.r.mt.......W vs..................
o^" > 7././l./.4s.....
. 7./.8./.85.....7/B./qs.....
7
. /.8 s......
nne r nu ain oo noi nncu o24o OFFICIAL RECORD COPY