ML19341B051
| ML19341B051 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/19/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-004, CON-NRC-TMI-81-4 NUDOCS 8101300098 | |
| Download: ML19341B051 (6) | |
Text
_
_~. - -
WA p *** coq s
70 UNITED si ATEs
'g y
,.(
p, NUCLEAR REGULATORY COMMISSION g.
' - C W ASHING TON, D. C. 20555 s
/
January 19, 1981
- P*
i:RC/TMI-81-004 I
l' MEMORANDUM FOR:
Harold R. Denton, Director, j
Office of Nuclear Reactor Regulation i
Bernard J. Snyder, Director, TMI Program Office FROM:
Lake H. Barrett, Acting Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of January 11 - 17, 1981.
Lake H. Barrett Acting Deputy Program Director TMI Program Office
Enclosure:
As stated I
cc w/ encl:
A Commissioner's Technical Assistants i
NRR Division Directors e
NRR A/D's J44,O f[2 fpg A r$~
C Regional Directors (q v., ec44p'o,%
,y IE Division Directors d
X005 Q
v %,7 4
X0MA br/7gg TII Program Office Staff (15) y EPA RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser 1
i
(
s101 s ooO9g-
f4RC IMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of January 11-17, 1981 Plant _ Status Core Cooling Mode:
Cyclic natural circulation in the reactor coolant system (RCS) loops with heat transfer to reactor building ambient.
Available Core Cooling Modes: Long-term cooling "B" (once through steam generator B); decay heat removai systms, e
RCS Pressure Control Mode:
Standby pressure control (SPC) system.
Backup Pressure Control Mode: One decay heat removal pump to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST).
Major Parameters (as of 0500, January 16,1981) (approximate values)
Average Incore Thermocouples: 122 F Maximum Incore Thermocouple:
154 F RCS Loop Tempratures:
A B
Hot Leg 119 F 122 F Cold Leg (1) 83 F 66 F (2) 85 F 68 F RCS Pressure:
104 psig (DVM)
Pressurizer Temperature: 69 F Reactor Building: Temperature:
62 F Water level:
Elevation 290.5 ft. (8.0 f t. from floor) via penetration 401 manometer Pressure:
-0.3 psig (Heise)
Concentration:
1.5 x 10-4 uCi/cc (Kr-85) (sample taken 1/14/81)
Effluent and E_nvironmental (Radiological) Information 1.
Liquid effluents from TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with f;RC requirements and City of Lancaster Agreement dated February 27, 1980.
During the semi-annual reporting period, July 1, 1980, -
December 31, 1980, the licensee reported that minute amounts of contamination with an origin froni Unit 2 was discharged from the TMI site.
The f4RC TMI Program Office staff verified that no accident related water, as defined in the City of Lancaster Agreement dated February 27, 1980, was discharged from Unit 2.
Although the
2 concentrations of radioactive ef fluent were not detectable at the discharge point, calculations indicated that less than one ten thousandth (0.0001) of a curie of Cesium 137 (Cs-137) was discharged.
This represents less than 0.001% of the permissable total liquid effluent activity as specified in Technical Specifications for other operational commercial power reactors.
2.
EPA Environmental Data.
Results from EPA monitoring of the environment aroun M D C Tte were as folloWs:
y 3
The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:
Location Jar.uary 5 - January ___9,1981 (pCi/m3)
Bainbridge 25 Goldsboro 23 Observation Center 22
- Middletown 24 All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and gama rate networks during the period from January 7,1981, through January 15, 1981.
3.
NRC_ Environmental Da_ta.
Results from URC monitoring of the environment around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
_ uCi/cc)
Sample Period (uCi /_cc )
(
HP-250 January 8, 1981-January 15, 1981
<9. 4 E-14 <9. 4 E-14 4.
_ Licensee Rad _f oa_ctive Material and Radwaste Shipment _s.
The following shipment was made:
On Monday, January 12,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Tuesday, January 13, 1981, e drum containing a section of HPR-211 cable from Unit 2 was shipped to EG&G Idaho, Inc.,
3 On Tuesday, January 13, 1981, a drum containing two vibration amps and a section of HPR-211 cable from Unit 2 was shipped to Sandia National Laboratory, Albuquerque, New Mexico.
On Wednesday, January 14,1981, a Unit 1 1,000 ml waste evaporator condensate storage tank (WECST) monthly composite and a 1,000 ml decay heat "A" sample were sent to Teledyne 3
Isotopes, Westwood, New Jersey, On Thursday, January 15,1981, Unit 2 compacted and non-e compacted low specific activity (LSA) waste was shipped to Nuclear Engineering Company, Richland, Washington.
Major Activities 1.
Reactor __ Decay Heat Removal.
Reactor decay heat continues to be removed by heat transfer from the RCS to reactor building ambient.
The secondary plant is being put in a long tenn layup condition.
Since steaming was secured on the "A" 0TSG one period of RCS flow occurred on January 14, 1981.
No further reporting in this area will be made unless a change in cooling mode occurs.
2.
Rgactor B_uildjng _P_ urge / Entry.
The sixth reactor building entry is scheduled for Tdbruary 3 and 5,1981.
The major activities to be perfonned include installation of. a closed circuit television system, work on the source range monitor, and a decontamination test. The day between the entries will be used to partorm circuit checks and prepare personal equipment needed by members of the entry team.
3.
Contaminated B_uilding Expan_s_ ion Joint. The licensee is finalizing a status report on efforts to detennine the extent of contamination of building expansion joints previously reported on December 27, 1980.
This report is due to the onsite NRC staff early next week.
4.
Grou_nd Water Mo_nitoring Status.
The licensee continued their well monitoring program and investigation into the possible source of the trace cesium contamination in well No. 2 located near the BWST (see attached figure).
Samples taken from well No. 2 on January 7,1981, were independently analyzed by the EPA, PA DER and NRC, confirming trace levels of Cs-137 in the Ps to 50 pCi/l range.
The PA DER also reported less than detectable levels of strontium-90. These levels are less than EPA drinking water standard concentrations.
The licensee also reported that additional well No. 2 samples taken during December and early January indicated an average Cs-137 concentration of approximately 30 pCi/1.
Licensee and NRC investigations are continuing. On January 15, 1981, the licensee inspectsd the 15 well locations including the area near well No. 2 and the BWST, accompanied by the NRC.
Preliminary conclusions proposed by the licensee indicate that the source of the trace cesium contamination could have resulted from previous leakage of contaminated water from the BWST into the soil. This
._ -. - =- _---__
i i
4 i
i conclusion is supported by the analysis of free-standing water the j
licensee collected from an excavation ditch near the BWST on January 12, 1981.
Although not part of the well monitoring program, analyses indicated Cs-134 and Cs-137 concentrations of 220+85 pCi/l and 870+120 pCi/1, respectively.
It is also important to note that the level at which this free-standing water was collected is above the level of water r
in the containment sump. The licensee is continuing the well monitoring program including expedited sample analyses for well No. 2.
Future Meetings 1.
On Thursday, January 22, 1981, L. Barrett and R. Conte will attend a public briefing in Harrisburg at the Forum, beginning at 7:30 p.m.,
sponsored by the Department of Environmental Resources concerning the status of decontamination at Three Mile Island.
Following the j
presentation, the NRC, EPA and Metropolitan Edison Company will be available to answer questions.
i 2.
The NRC's Advisory Panel for the Decontamination of Three Mile Island, Unit 2, will hold meetings in Harrisburg, on February 4,11 j
and 19,1981 The public is invited to observe all three of these i
meetings, which will be held at the Forum of the Education Building on Cmanonwealth and Walnut Streets.
Each of these meetings are scheduled to begin at 7:00 p.m. and end at 10:30 p.m.,
3 S
9 e
LOCATION OF TMI MONITORING WELL #2 NORTH ^,'.
y' i
BORATED WATER STORAGE TANK f
Well #2 l
EPICOR 11 b
}
[
G
,ew,-
W i
/
E o.
w 4
50 2*
co tr a n
h V
u
- O t
Aux. BloG a
m UN T d I
TOR
@C H ANDLWG ' RE A{DG FUEL i
BL DIES EL
~,
G E. N.
GLb G.
_l' I
L I
v4tfl0 Of Afl8 I
%LCLgan agewhatCav COMM 88404 eas =ofoe e t Mt**
pogf aQI 6 fil8 Pa1D ggg
,acenow, Gemeeeen oreigias 3445H L
-J f
e S
i e
i
-