ML19344A933
| ML19344A933 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/11/1980 |
| From: | Jay Collins NRC - NRC THREE MILE ISLAND TASK FORCE |
| To: | Harold Denton, Snyder B NRC - NRC THREE MILE ISLAND TASK FORCE, Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-124 NUDOCS 8008250051 | |
| Download: ML19344A933 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 2055S e
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August 11, 1980 i4RC/TMI-80-124 i
fiEi10RANDUM FOR:
H. R. Denton, Director, Office of Nuclear Reactor Regulation B. J. Snyder, Program Director, TMI Program Office FROM:
J. T. Collins, Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the week of August 3-9, 1980.
/ f&
John T. Collins Deputy Program Director TMI Program Office
Enclosure:
As stated cc: ED0 OGC Office Directors Commissioner's Technical Assistants l
NRR Division Directors NRR A/D's Regional Directors IE Division Directors X00S X0MA HW EPA RO&NS Branch Chief, Region I Public Affairs, Region I T. Elsasser TMI Program Staff s o o se sooSI g
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of August 3-9, 1980 Plant Status Core Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant
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system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient.
Available Core Cooling Modes: 0TSG "B" to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode:
Makeup system in conjunction with letdowl flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0500, August 8,1980) (approximate values)
Average Incore Thermocouples: 141 F Maximum Incore Thermocouple:
186 F RCS Loop Temperatures:
A B
Hot leg 139 F 142 F Cold Leg (1) 97 F 100 F (2) 89 F 103 F RCS Pressure: 94 psig (Heise) 96 psig (DVM-controlling)
Pressurizer Temperature:
90 F Reactor Building:
Temperature:
86 F Water level: Elevation 290.4 ft. (7.9 ft from floor) via penetration 401 manometer Pressure:
-0.6 psig (Heise)
Concentration: 1.38 x 10-3 uCi/cc (Kr-85)
Environmental & Effluent Information 1.
Liquid effluents from TMI-l released to the Susquehanna River, after processing, were within the limits specified in Technical g
Specifications.
2.
No liquid effluents were discharged from TMI-2.
3.
Results from EPA monitoring of the environment around the TMI site were:
2 The EPA measured.Kr-85 concentrations (pCi/m3) at several environmental monitoring stations and reported the following results:
Locatica July 18-25, 1980 July 25-August 1,1980 (pCi/md)
(pCi/mJ)
Bainbridge 24 64 Goldsboro 24 31 Observation Center 27 37 Middletown 23 43 Hills Island 27 Data not available EPA environmental stations registered background levels for air particulate and water samples.
Gamma scan results for all sampling locations were negative.
Instantaneous direct radiation readings showed an average level of 0.013 mram/hr for the 18 monitoring stations.
4.
NRC Environmental Data The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HPR-227 July 30 - August 6, 1980
<6.9E-14
<6.9E-14 No reactor related radioactivity was detected.
Environmental TLD measurements for the period July 2 to July 31,1980, indicate gamma radiation to be at the natural background levels.
Fifty-seven TLD's registered doses ranging from 0.11 mR/ day to 0.18 mR/ day.
Average dose was 0.14 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
5.
Radioactive Material and Radwaste Shipments were as follows:
On Monday, August 4,1980, a 40 misunit 2 reactor ~ coolant sample and a 250 ml EPICOR II effluent sample were shipped to Babcock & Wilcox (B&W), Lynchburg, Virginia.
On Tuesday, August 5,1980, a dirt sample from the EPICOR I shield storage area was sent to Science Applications Incor-porated (SAI), Rockville, Maryland.
On Tuesday, August 5,1980, two Unit 2 bleed tank samples from RCBT-B and RCBT-C were sent to the Oak Ridge National Laboratory, Oak Ridge, Tennessee.
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3 On ' Tuesday, August 5,1980,-Smear Samples from the Unit 2
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reactor building and shoe covers used by entry personnel were shipped to' Exxon Nuclear Laboratories, Idaho Falls, Idaho.
s On Tuesday, August 5,1980, an EPIC 0R I dewatered resin liner (D-19) was shipped to Nuclear Engineering Company, Inc.,
Richland, Washington.
On Thursday, August 7, 1980, an EPICOR I dewatered resin liner
. (P-10) was shipped to Nuclear Engineering Company, Incorporated, Richland, Washington.
On Friday, August 8,1980, an air sample from Unit 2 auxiliary building, AMS B-4, was sent to Science Applications Incorporated (SAI), Rockville, Maryland.
On Friday, August 8,1980, a 1000 m1 sample of Unit I waste evaporator cc..densate storage tank-A was sent to Teledyne Isotopes, Westwood, New Jersey.
fjajor Activities This Wee.k 1.
EPICOR II System The total process effort as of August 6,1980, is 474,000 gallons.
A restart of EPICOR II is scheduled for Monday, August 11, 1980, to process approximately 28,000 gallons from the reactor coolant bleed tank 'B'.
The accumulated RCBT 'B' water is due to general decontamination flushing and tank transfers. The processing is expected to be
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completed for the scheduled two week outage beginning August 13, 1980.
The major work effort is to improve personnel safety related items.
2.
Reactor Building Purge The Deputy Program Director of the TMI Program Office has authorized the licensee to release up to 72 curies of Kr-85 per week.
Continued purging of small quantities of Kr-85 is required to release Kr-85 which continues to accumulate in the reactor building.
Krypton-85 sources include the waste gas decay tanks in the auxiliary building and offgassing from the water in the reactor building sump.
Krypton concentrations in the reactor building are being kept as low as porsib1 to minimize exposure to reactor building entry teams.
3.
Reactor Building Entry
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The second post-accident entry into tje thrit'2Teactor building is scheduled for August 15, 1980. The entry will be made by four iTidividuals and'will include surveys of the upper level of the reactor ouliaing.
The planned ' duration of the entry is 40 minutes.
The entry team will wear protective clothing similar to the type worn during the first entry.
The self-contained air breathing unit 7.
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4 aill not be used. Based on the results of the air surveys taken during the first entry, the licensee has elected to use a powered air filter with a pressurized face piece to protect against airborne acti vi ty.
5 The entry team will take photographs and will perfom radiological surveys on 305' and 347' levels.
A teletector reading in the vicinity of the reactor head is planned.
The team will replace an area radiation monitor on the 305' elevation.
The old monitor will be retrieved as will other preselected objects which will be used to quantify tre radiation exposure and the degree of surface contamination.
l 4.
Decay Heat Valve' f
On Friday, August 8,1980, one of the reactor coolant system's l
boundaries was extended by controlled and planned procedures.
The boundary was previously located within the containment building, but is presently at the 280'6" elevation pioing of the decay heat removal system in the fuel handling building.
This boundary change was achieved by opening decay heat valve #1.
This was necessary to pennit the near future operation of the mini-decay heat removal system.
The valve that was opened (DH-V1) is located in the piping that would normally take suction from the reactor vessel for decay heat system operation. The valve has been closed since before the TMI-2 accident on March 28, 1979.
Isolation of the reactor coolant system is presently being maintained by valve DH-V3, which is downstream of DH-V1, just before the mini-decay heat system tie-in.
Prior to the opening of DH-V1, the radiation levels in the area of the piping downstream of DH-V3 were less than 100 mr/hr and the area above the valve was reading less than 100 mr/hr.
After the valve was opened, the area of the piping downstream of DH-V3 still l
read less than 100 mr/hr and the area above the valve has increased l
as expected to approximately 3 r/hr at contact with the pipe.
The I
downstream levels indicate that there is no detectable leakage l
through DH-V3 and the increased levels above the valve indicate i
that the upstream contains reactor coolant.
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5.
Weekly Boron Analysis.
d Due to contamination from a radiation spill at the B&W laboratory, I
the lab was not able to analyze the RCS sample from TMI-2.
The licensee is now beyond the 7 day technical specification surveillance frequency and notified the TMI Program Office on Friday, August 8,1980, of the problem.
Plans are being prepared to perform a boron analysis on-site on Monday, August 11, 1980, if the B&W lab is not operable by that time.
The licensee has no reasori 10 suspect the boron concentration to be out of specification since no changes affecting boron concentration have been made to the RCS.
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