ML20154A331
| ML20154A331 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/24/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-020, CON-NRC-TMI-86-20 NUDOCS 8603030378 | |
| Download: ML20154A331 (4) | |
Text
Q9
,m e
! ' k f [.
\\ W;;
s l
,v j,
February 24, 1986 NRC/THI-86-020 4-l l
MEMORANDUM FOR:
. Harold R. Denton, Director Office of Nuclear Reactor Regulation e
s Fran( J. Miraglia, Director Ofvision of PWR Licensing-B T
FROM:
William D. Travers, Director jy?
THI-2 Cleanup Project Directorate l ~
SUBJECT:
HRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS i
a.
REPORT FOR FEBRUARY 15 - FEBRUARY 23, 1986-
[
1.
DEFUELING E
As of February 24, 1986, 16 defueling canisters have been a
transferred from the reactor vessel to the spent fuel pool storage racks. Total weight of fuel debris and structural-material l'
transferred out nf the reactor vessel is about 12,500 lbs. The estimated total weight of fuel debris and structural materials originally in the reactor vessel after the accident was 308,000 lbs.
l Defueling continued with filling fuel canisters with the spade-bucket tool. Each of the six most recently filled defueling i a canisters contains a net fuel debris weight of over 1,100 lbs. The 3:
licensee's target is to fill one fuel canister each day. -However, this target has been achievable only at times when visibility in the e
i l
reactor was relatively good, l<
The bio-organism growths in the reactor vessel is severely affecting visibility. The only reactor water cleanup system currently available to the ifcensee is the Temporary Reactor Coolant l,,
Filtration System (TRCFS). This system started operation on February 15, 1986 Operation of the system is limited to times when no defueling is taking place. Otherwise, the fine particles stirred up by defueling would adhere to the filter media and rapidly increase the dose rate from the filter assembly. By February 20, J
1906, the system has run for over 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> and processed about 150,000 gallons of reactor water. Until a permanent method to f'
respond to the bio-organism rowth problem, the operation of the
!j, 1RCfS is essential for. dafue ing to continue.
//
g t
860303C'378 B60224 PDR AbOCK 05000320-R PDR l-j oneses>
- a
............m..
........m.
................m..
t
....*..m
..m..
...m
- m..
m.
+..m.
...m.a......
..m..m......m em>
...m..
m...
....m
- ...m m.m...m mm....
m.
..m....
..mm.
mee m mm.m N:c ronu sis tio son nacu o24o OFFICIAL RECORD COPY
d Ilarold R. Denton 2
February 24, 1986 Frank J. !!iraglia NRC/THI-86-020
~
~2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere.
The reactor vessel head is in storage on the 347' elevation. The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam is installed between the deep and shallow ends of the transfer cenal, pemitting a 20 foot depth (about 5 feet over the top of the plenum).
Reactor Coolant System (RCS) cooling is by natural heat loss to the reactor building almasphere. Calculated reactor decay heat is near 10.7 kilowatts.
Incore themocouple readings range from 71*F to 96 F, averagtag 81*F.
The average reactor building temperature is 50*F.
The reactor building airborne activity at the defueling platfom is 6.7 l
E-8 uCi/cc Tritium and 5.4 F-11 UCi/cc particulates, predoninately Cesium-137.
The reactor vessel and modified internal indexing fixture are flooded to the 327'6" elevation which is 151 feet above the core l
region top. The defueling platfom is mounted above the internals indexing fixture.
3.
HASTE fANAGEftENT The Submrged Demin!ralizar System (SDS) correnced processing batch 127, Fuel Transfer Canal Recycle through both trains.
EPICOR II reaained s 1utdown.
Total volu:ne processi d tnrough SDS to date is 3,682,029 gallons, and the total volume proussed through EPICOR II is 2,822,953 gallons.
4.
DOSE REDUCTION /DECONTA!!!'iATION Average general area rMiiation dose rate is 40 mrem per hour on the 347' level of the reactir building and is 67 mrem per hour on the 305' level of the reacto r building. The average dose rate to workers on the defuelins work platform is 8 nrem per hour.
5.
EllVIROHl1 ENTAL N0 flit 0 RING l
US Envirqnmental Protect 1:n Agency (EP$) sample analysis results l
show TMI site liquid effloants to be in accordance with regulatory l
limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge to the river l
consisted of seven daily ccaposite samples takea from February 1 through February 8,1986. / gama scan detected no reactor related activity.
The Lancaster water sample t; ken at the water works intake and l
analyzed by EPA consisted of a seven day composited sample taken from February 2 through Febru try 8,1986. A gami scan detected no reactor related radioactivity, i
k l s-Aw k
^">
sic ro nu ais no um u nc" ""
OFFICIAL RECORD COPY
T
+
Harold R. Denton 3
February T4,1986 Frank J. iiiraglia NRC/T!11-86-020 The NRC outdoor airborne particulate sampler at the Trti site collected a sample between February 12, and February 19, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
6.
REACTOR BUILDING ACTIVITIES Initial defueling of the reactor core is in progress.
7.
AUXILIARY AND FUEL !!A. IDLING BUILDING ACTIVITIES Installation of the balance of Defueling Water Cleanup System (DUCS) l and canister dewatering systea continued.
Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
Preparations are being made for decontamination in the Seal l
l Infection Room, 281' auxiliary building.
8.
HRC EVALUATIONS IN PROGRESS Technical Speciff cation Change Request number 49.
Recovery 0parations Plan Chinge number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Defueling Water Cleanup System Technical Evaluation Report, l
i Revision 7.
Containnent Air Control Envelope Technical Esaluation Report, l
Revision 5.
Solid uaste Facility Technical Evaluation Repart.
Reactor Building Sunp Criticality Safety Evaluation Report, original signed by C.J. Cowgill for William D. Tra"ers Director T'11-2 Cle1nup Project Dircctorato 1
l l
i
"'C'>
............e
............e
^">
..........y n:.c ro.,u ns oo soi sscu ou OFFICIAL RECORD COPY
g-QLy.-
-i Harold R. Denton 4
February 24, 1986 9
Frank J.111raglia' NRC/THI-86-020 INTERNAL DISTRIBUTION EDO OGC Office Directors Connissioner's Technical Assistants
!!RR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS i'
THI Cleanup Project Directorate (10)
RI Division Directors Public Affairs, RI State Liaison, RI TMIPO HQ r/f THI SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File 1
l 11 s
r if t
f, i-ltr l-
~M p- >l.T.eir.c.e.D.@de rii.ce.D t<.'.. g.g.g.Tmce.n.e
.............l j**">.0,cq,tu L,Ccowgin Tech Support.WTeavets.................. 2A/.as..... 2.at/.qq.... m4/.ac..... a486,..... ~ "a'
- NRc,om sie noe0(NRCM OMO OFFICIAL RECORD COPY}}