ML19276H358: Difference between revisions
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{{#Wiki_filter:* | {{#Wiki_filter:* | ||
. i, . .,. ,,,, ,-- | . i, . .,. ,,,, ,-- | ||
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. . - . ',.s.- ,, | . . - . ',.s.- ,, | ||
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. ENCLOSURE (2) l3 L | . ENCLOSURE (2) l3 L | ||
' 06 0 jf Metropolitan Edison Company . | |||
' 06 0 jf | |||
Metropolitan Edison Company . | |||
nrce Mile Island Nucicar Station, Unit 1 (TMI-1) | nrce Mile Island Nucicar Station, Unit 1 (TMI-1) | ||
Docket No. 50-289 Operating License No. DPR-50 ~ | 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 | |||
Report of Three Unplanned | |||
: 1. Exposures and Concentrations of Radioactive Material - | : 1. Exposures and Concentrations of Radioactive Material - | ||
. . . . . h+ .. . . | . . . . . h+ .. . . | ||
Note: . | 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 . | **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.** | 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) | |||
- In accordance with the requirements of 10 CFR 20.405(a), the following | October 6 I 6.95 x 10-9 II - | ||
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 | |||
II - | |||
1.15 x 10-8 . | 1.15 x 10-8 . | ||
. October 8 4.1 x 10-8 | . 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 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. | ||
October 9-10 4.3 x 10-8 | |||
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. | |||
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 | 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'' | ||
In ''' v. Actual Exposure (cret No . f. Calc. Max.* | |||
In ''' v. Actual Exposure (cret | |||
No . f. Calc. Max.* | |||
Release Expose Pk t . Dos . Film Badge Dosage (crem) | Release Expose Pk t . Dos . Film Badge Dosage (crem) | ||
Oct. 6 I O 0 0 0 II 2 'O <10 | 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 | |||
" 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: | * 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 | 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 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. | ||
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 , | 'following values are given for the theoretical maximum concentration of radioactive caterial at the 281-foot level of the Auxiliary , | ||
| Line 131: | Line 55: | ||
October 6 I - | October 6 I - | ||
2.65 x 10-3 . | 2.65 x 10-3 . | ||
II 4.4 x 10-3 | II 4.4 x 10-3 October 8 1.5 x 10-2 October 9-10 1.66x10-h | ||
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. | : 2. Causes of Exposures and Concentrations Picase see section 2, enclosure (1), of this submittal. | ||
: 3. Corrective Actions 14l.p:33 ; . | |||
: 3. Corrective Actions | |||
14l.p:33 ; . | |||
. Picase see section 4, enclosure (1), of this submittal. - | . Picase see section 4, enclosure (1), of this submittal. - | ||
: h. y | : h. y | ||
- D**D *D N . | - D**D *D N . | ||
wo e 2. - | wo e 2. - | ||
La | La | ||
. ..{,,, | . ..{,,, | ||
:- , , ,, , : ..- l ,', . ,.. - | :- , , ,, , : ..- l ,', . ,.. - | ||
: 4. Personnel exposut data is provided in accordance with 10 CFR 20.405(b) as fo11cus : , | |||
: 4. Personnel exposut data is provided in accordance with 10 CFR | |||
20.405(b) as fo11cus : , | |||
Date'of . | Date'of . | ||
Social Security Date of Incident Individual | Social Security Date of Incident Individual Ea timated Nudoor Birth Exposure (crea) | ||
Oct.'6 I NO INDIVIDUALS EXPOSED II James, David C. 385-44-8174 7/24,45 | |||
Ea timated 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 Taira, Leo 2/04/18 <10 | <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 | -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{ , | ||
(o SNb{ , | |||
e | e | ||
+ . | + . | ||
!419 332' - | !419 332' - | ||
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Revision as of 16:54, 1 February 2020
| 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
. i, . .,. ,,,, ,--
. > . G . . *l. . a . .' l. , .
. . - . ',.s.- ,,
. .y .;-
. ENCLOSURE (2) l3 L
' 06 0 jf 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 II -
1.15 x 10-8 .
. 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 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.
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
In v. Actual Exposure (cret No . f. 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 cc ** Note: On October 9, 3 1974, the DRO Region 1 Air Flow = 50 FT /nin 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)
October 6 I -
2.65 x 10-3 .
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 .
wo e 2. -
La
. ..{,,,
- - , , ,, , : ..- l ,', . ,.. -
- 4. Personnel exposut data is provided in accordance with 10 CFR 20.405(b) as fo11cus : ,
Date'of .
Social Security Date of Incident Individual Ea timated 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 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 (o SNb{ ,
e
+ .
!419 332' -
e
, g
- e y e