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| document report number = NUDOCS 7910160694 | | document report number = NUDOCS 7910160694 | ||
| package number = ML19276H306 | | package number = ML19276H306 | ||
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO | | document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT | ||
| page count = 3 | | page count = 3 | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:., | ||
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. ENCLOSURE (2) l3 L | |||
0 0 jf 6 | |||
Metropolitan Edison Company nrce Mile Island Nucicar Station, Unit 1 (TMI-1) | |||
Docket No. 50-289 Operating License No. DPR-50 | |||
~ | |||
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) | 30-Day Report as Required by 10 CFR 20.405(a)(2), and 20.403(a)(2) | ||
~ | |||
Report of Three Unplanned Radioactive Releases Occurring on October 6, 8, and 9-10,1974 1. | |||
Exposures and Concentrations of Radioactive Material h+ | |||
Note: | |||
**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.** | |||
- In accordance with the requirements of 10 CFR 20.405(a), the following 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: | |||
Report of Three Unplanned | Calculated 24-Hour Average Concan-Release tration of Radioactive Material at the Closest Downwind Unrestricted Area (tici/ce) | ||
October 6 I | |||
6.95 x 10-9 1.15 x 10-8 II | |||
. October 8 4.1 x 10-8 October 9-10 4.3 x 10-8 The corresponding 10 CFR 20, Appendix B, Table II MPC value as cal-a 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. | |||
Note: | 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 | |||
~ | |||
limits in 10 CFR 20.** | |||
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: | |||
Release | |||
(tici/ce) | |||
October 6 | |||
1.15 x 10-8 | |||
October 9-10 | |||
The corresponding 10 CFR 20, Appendix B, Table II MPC | |||
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 | |||
7910156(fg'' | 7910156(fg'' | ||
No. | |||
f. | |||
In ''' v. | |||
Actual Exposure (cret Calc. Max.* | |||
Release Expose Pk t. Dos. | |||
In ''' v. Actual Exposure (cret | Film Badge Dosage (crem) | ||
Oct. 6 I O | |||
0 0 | |||
Release | 0 II 2 | ||
Oct. 6 I | 'O | ||
<10 | |||
" 3.23 Oct. 8 5. | |||
O | |||
Oct. 9-10 | <10 159 Oct. 9-10 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: | 0 0 | ||
Volume of room = 2.38 x 108 | 0 | ||
* Note: | |||
Oct. 6 I | 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 | |||
** Note: | |||
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. | On October 9, cc 3 | ||
Air Flow = 50 FT /nin 1974, the DRO Region 1 Radioactivity Released Office was infor=ed that 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 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. | |||
In accordance with the requirements of 10 CFR 20.405(a), the | 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: | |||
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) 2.65 x 10-3 October 6 I II 4.4 x 10-3 October 8 1.5 x 10-2 October 9-10 1.66x10-h 2. | ||
Calculated 24-Hour Average Concen-Release | Causes of Exposures and Concentrations Picase see section 2, enclosure (1), of this submittal. | ||
3. | |||
2.65 x 10-3 | Corrective Actions 14l.p:33 ; | ||
II | . Picase see section 4, enclosure (1), of this submittal. | ||
h. | |||
October 8 | y D**D | ||
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La wo e | |||
14l.p:33 ; | |||
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wo | |||
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4. | |||
Personnel exposut data is provided in accordance with 10 CFR 20.405(b) as fo11cus : | |||
Date'of Social Security Date of Ea timated Incident Individual Nudoor Birth Exposure (crea) | |||
Oct.'6 I NO INDIVIDUALS EXPOSED II James, David C. | |||
385-44-8174 7/24,45 | |||
<10 Tilley, G. J. | |||
204-34-6889 5/15 /45 | |||
<10 Oct. 8 Downs, Bernard W. | |||
20.405(b) as fo11cus : | 469-07-0743 2/04/18 | ||
<10 Taira, Leo | |||
-041-30-6608 5/09/37 | |||
<10 Matarazzi, Clyde 178-40-5354 3/13/47 | |||
<10 Fisher, R. | |||
Date'of | 162-44-0754 Age: 22 | ||
Social Security | <10 Larson, A. | ||
519-18-5933 Age: 52 | |||
<10 Oct. 10 NO INDIVIDUALS EXPOSED (o | |||
Oct.'6 I | SNb{, | ||
II James, David C. | |||
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Latest revision as of 01:14, 3 January 2025
| 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
.,
. >. G.. *l..
a..' l.,
',.s.-
. i,
..y.;-
. ENCLOSURE (2) l3 L
0 0 jf 6
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)
~
Report of Three Unplanned Radioactive Releases Occurring on October 6, 8, and 9-10,1974 1.
Exposures and Concentrations of Radioactive Material h+
Note:
- 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.**
- In accordance with the requirements of 10 CFR 20.405(a), the following 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-Release tration of Radioactive Material at the Closest Downwind Unrestricted Area (tici/ce)
October 6 I
6.95 x 10-9 1.15 x 10-8 II
. October 8 4.1 x 10-8 October 9-10 4.3 x 10-8 The corresponding 10 CFR 20, Appendix B, Table II MPC value as cal-a 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.
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
~
7910156(fg
No.
f.
In v.
Actual Exposure (cret Calc. Max.*
Release Expose Pk t. Dos.
Film Badge Dosage (crem)
Oct. 6 I O
0 0
0 II 2
'O
<10
" 3.23 Oct. 8 5.
O
<10 159 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
- Note:
On October 9, cc 3
Air Flow = 50 FT /nin 1974, the DRO Region 1 Radioactivity Released Office was infor=ed that 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 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.
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) 2.65 x 10-3 October 6 I II 4.4 x 10-3 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.
3.
Corrective Actions 14l.p:33 ;
. Picase see section 4, enclosure (1), of this submittal.
h.
y D**D
- D N 2.
La wo e
..{,,
,,,,, :..- l,',.
4.
Personnel exposut data is provided in accordance with 10 CFR 20.405(b) as fo11cus :
Date'of Social Security Date of Ea timated Incident Individual Nudoor Birth Exposure (crea)
Oct.'6 I NO INDIVIDUALS EXPOSED II James, David C.
385-44-8174 7/24,45
<10 Tilley, G. J.
204-34-6889 5/15 /45
<10 Oct. 8 Downs, Bernard W.
469-07-0743 2/04/18
<10 Taira, Leo
-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 (o
SNb{,
e
+
!419 332' e
g e
y e