ML19276H358
| ML19276H358 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/24/1974 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19276H306 | List: |
| References | |
| NUDOCS 7910160694 | |
| Download: ML19276H358 (3) | |
Text
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. ENCLOSURE (2) l3 L
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Metropolitan Edison Company .
nrce Mile Island Nucicar Station, Unit 1 (TMI-1)
Docket No. 50-289 Operating License No. DPR-50 ~
30-Day Report as Required by 10 CFR 20.405(a)(2), and 20.403(a)(2)
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Report of Three Unplanned
- Radioactive Releases Occurring on October 6, 8, and 9-10,1974
- 1. Exposures and Concentrations of Radioactive Material -
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Note: .
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- In no case did any member of the public or any plant or contractor personnel receive a radiation dose in excess of the applicable .
limits in 10 CFR 20.**
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- In accordance with the requirements of 10 CFR 20.405(a), the following
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values are given for the theoretical maximum concentration of radio-active material to which a member of the public could have been exposed as a result of the' four releases unoer discussion:
, Calculated 24-Hour Average Concan-
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Release tration of Radioactive Material at the Closest Downwind Unrestricted Area
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(tici/ce)
October 6 I 6.95 x 10-9
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1.15 x 10-8 .
. October 8 4.1 x 10-8
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October 9-10 4.3 x 10-8
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The corresponding 10 CFR 20, Appendix B, Table II MPC a value as cal-culated from ga=ma spectrometry data on actual samples of released radiogas is 2.42 x 10-7 pCi/cc. By co=parison, all of the values reported above for the general public are lower than this value.
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We following values are given for the theoretical maxi =um dosages khich those individuals who were working on the 281-foot level of the Auxiliary Building during the releases could have received. Also given, for comparison, are the actual exposures receivedt j ] } } } Q
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7910156(fg
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In v. Actual Exposure (cret
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No . f. Calc. Max.*
Release Expose Pk t . Dos . Film Badge Dosage (crem)
Oct. 6 I O 0 0 0 II 2 'O <10
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" 3.23 Oct. 8 5. O <10 159
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Oct. 9-10 0 0 . 0 0
- Note: Figures are on a per individual basis. Please also note that the following values were used in deriving the calculated maximum dosage figures:
Volume of room = 2.38 x 108 cc ** Note: On October 9, 3 1974, the DRO Region 1 Air Flow = 50 FT /nin Radioactivity Released Office was infor=ed that
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Oct. 6 I 5.84 Ci this figure was 74 C1. S ub-II 9.62 C1' sequent analyses , however, Oct. 8 34 Ci ** indicate that 74 Ci was overly Oct. 9-10 37 Ci conservative and 34 Ci is corre
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From this it can be seen that the method used to calculate the theoretical maximus dosages was highly conservative and that no radiation worker received a significant exuosure as a result of th'c releases.
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In accordance with the requirements of 10 CFR 20.405(a), the
'following values are given for the theoretical maximum concentration of radioactive caterial at the 281-foot level of the Auxiliary ,
Building during the releases:
Calculated 24-Hour Average Concen-Release tration of Radioactive Material at the 281-Foot Level of the Auxiliary Building (uC1/cc)
October 6 I -
2.65 x 10-3 .
II 4.4 x 10-3
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October 8 1.5 x 10-2 October 9-10 1.66x10-h
- 2. Causes of Exposures and Concentrations Picase see section 2, enclosure (1), of this submittal.
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- 3. Corrective Actions
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. Picase see section 4, enclosure (1), of this submittal. -
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- 4. Personnel exposut data is provided in accordance with 10 CFR
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20.405(b) as fo11cus : ,
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Date'of .
Social Security Date of Incident Individual
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Ea timated Nudoor Birth Exposure (crea)
Oct.'6 I NO INDIVIDUALS EXPOSED
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II James, David C. 385-44-8174 7/24,45
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<10 Tilley, G. J. 204-34-6889 5/15 /45 <10 Oct. 8 Downs , Bernard W. 469-07-0743 Taira, Leo 2/04/18 <10
-041-30-6608 5/09/37 <10 Matarazzi, Clyde 178-40-5354 3/13/47 <10 Fisher, R. 162-44-0754 Age: 22 <10 Larson , A. 519-18-5933 Age: 52 <10 Oct. 10 NO INDIVIDUALS EXPOSED
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