ML20054B999
| ML20054B999 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/06/1982 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | Barrett L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054C000 | List: |
| References | |
| 4400-82-L-0045, 4400-82-L-45, NUDOCS 8204190360 | |
| Download: ML20054B999 (3) | |
Text
DESIGNATE ORICIf7Ay,
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GPU Nuclear P.O. Box 480 U
GM Middletown, Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:
April 6, 1982 4400-82-L-0045 W
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Mr. L. H. Barrett, Deputy Program Direct U. S. Nuclear Regulatory Commission F
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Dear Sir:
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Three Mile Island Nuclear Station U tt c.3 g
Operating License No. DPR-73 A
Docket No. 50-320 Containment Integrity Assessment Program This is the periodic report presenting results of our ongoing effort to detect potential radioactive water leakage from the Containment Building.
The status of the various portions of this program are discussed below.
Groundwater Monitoring
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The following groundwater monitoring data is attached:
1.
Individual computer graphs (Figure 1) of tritium concentrations for each monitoring station and the East Dike Catch Basin (EDCB) up to and including January 6, 1982.
2.
Individual computer graphs (Figure 2) indicating water levels within the monitoring stations up to and including February 1, 1982.
3.
Computer tables (Tables 1 and 2) of gamma scan data up to and including February 1, 1982 for MW-2 (results for all other wells are through January 6, 1982).
4.
A graph indicating gamma scan data from Monitoring Station MW-2 (Figure 3).
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5.
A composite drawing showing all monitoring locations with a graph of the tritium concentrations for each station.
and 6.
A table (Table 3) indicating tritium concentrations in February March 1982 groundwater samples.
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7.
Individual graphs (Figure 4) of February, 1982 tritium concentrations for monitoring locations MW-2, OW-16, and OW-17.
8.
A graph indicating the Reactor Building Sump Water level (Figure 5).
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L. H. Barrett 4400-82-L-0045 Tritium concentrations for sampling dates December 2, 1981 and January 6, 1982 remained within the range seen in previou's samples.
The OW-13B sample taken on January 6, 1982 had a tr! tium concentration of 1940 ! 190 pCi/t.
The slightly higher readings in OW-13B may be attributable to contaminated runoff from the surfaces of the Unit 2 equipment hatch, which is a moderately contaminated area.
l Gamma results for the December,1981 and January, 1982 sampling dates are also reported herein.
In our last report, we reported that the December 2, 1981 MW-2 sample indicated a Cs-137 concentration of 15 ! 9.6 pC1/t. A recount of this sample failed to detect any Cs-137. Neither of the two analyses of this sample detected any Cs-134. The MW-2 sample of January 6, 1982 has been analyzed to have a Cs-137 concentration of 12.0 ! 7.4 pCi/t.
No Cs-134 was detected in this sample, either. No gamma emitters were detected in any of the other monitoring locations on the January or December sampling dates.
On January 13, 1982 Unit 2 BWST water leaked onto the ground surrounding well OW-16.
Consequently, soil in the spill area was collected and an accelerated ground water sampling program was initiated. The East Dike Catch Basin (EDCB) was sampled on the afternoon of January 13, 1982 and twice on January 14, 1982.
These four samples were sent to a radiological lab and analyzed.
The resulting concentrations were consistent with l
earlier data; this is, no significant increase in tritium or gamma activity were noted.
Daily samples were drawn from the EDCB during the week of January 18, 1982.
l Monitoring Station OW-16 was again sampled on January 21, 1982. These samples also showed normal levels.
I On January 29, 1982, OW-16 was again sampled and a tritium concentration of l
4770 t 290 pC1/1 was reported.
On the February 1, 1982 sampling date, tritium concentrations in both OW-16 and MW-2 showed elevated concentrations. As a result, groundwater samples were taken from various wells on February 9, 10, 11, 12, 16, 18, 23, and 25, and March 2, 9, 16, and 23, 1982.
February samples were split and analyzed by three different laboratories. The highest concentration (of results received to date) occurred in OW-17 on March 23, 1982 (1,100,000 110,000 pC1/t.
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Concentrations in MW-2 and OW-16 reached 954,000 pC1/1 and 362,000 pC1/1 respectively, on February 12, 1982 and March 2, 1982 respectively (See Table 3 and Figure 4).
Of the wells in the BWST area, OW-10 and MW-3 have also
-shown elevated concentrations. We have analyzed the samples for cesium and have seen no indication of its presence in any monitoring well for the February sampling dates.
l
e L. H. Barrett 4400-82-M-0045 Although we believe the January 13, 1982 leakage from the BWST is the source of the elevated tritium concentrations, efforts are continuing to identify and assess any other possible source of this contamination.
Water level data for the monitoring locations up to and including February 1, 1982 is contained in Figure 2.
Due to the delay in preparing this report, the March data was obtained prior to its issuance. This data has been included in Table 3, however, the Figures have not been updated with the most recent data in order to prevent further delay.
Cork Seal, Tendon, Access Callery and Containment Outer Wall Radiation Monitoring Continued surveillance of the tendon gallery, cork seal and outer wall have shown no indication of containment leakage or significant changes.
Reactor Building Sump Water Level Figure 5 presents sump level data for the period January 1, 1980 through March 12, 1982.
Sump level measurements continue to correspond to predicted levels within the accuracy of the measuring technique.
SDS processing decreased the sump level to 0.392 feet. The slight increase in sump level in the first two weeks of March, 1982 is attributed to water sprayed into the building in support of decontamination.
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J. J Barton I A g Director TMI-2 JJB:JJB:djb Attachments Dr. B. J. Snyder, Program Director TMI Program Office cc:
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