ML19224B289
| ML19224B289 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1977 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 1628, TM-0410, TM-410, NUDOCS 7906140397 | |
| Download: ML19224B289 (12) | |
Text
_s
~
~
TMI DOCUMENTS DOCUMENT NO:
' 8((
- g;a COPY MADE ON OF DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC 7906140397 197 079 e
...M.
1628
^
Revision 3 09/30/77 THREE MILE ISLAND NUCLEAR STATION
,{}]h[-
STATION HEALTH PHYSICS PROCEDURES 1628 PROGRAM FOR MEDICAL AND BI0 ASSAY EXAMINATI..
ONTROL D C0?Y Table of Effective Pages rage Date Revision Pace Date Revision Pace Date R evision 1.0 09/30/77 3
Il 09/30/77 3
2.0 09/30/77 3
21 09/30/77 3
3.0 04/08/74 1
4.0 08/20/75 2
4.1 08/20/75 2
5.0 08/20/75 2
6.0 04/08/74 1
7.0 04/08/74 1
8.0 04/08/74 1
3]
Unit 1 Staff Recomme pproval Unit 2 Staff Reco men s Approval Date _
Approval Date Approval Cogniz/nt M/ Head Cognhanhjfe/t. F end Unit 1 PORC Recommends Approval Unit 2 PORC R o ends Approval 9'
hk Ah hwrL~
Date 9-)$'77 Date Chairman of PORC p efus(
n of PORC PORC comments of included PORC comments of included 3
(date)
(data)
By Date By Date ~
ApprovfC @ t u hate 7-N'- 1 70 ~77 -
Station SJ;stn(dMn// * }9/[g^"'"
Unit Superintendent
t 1628 Revision 3 09/30/77 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURES 1628 PROGRAM FOR MEDICAL AND BI0 ASSAY EXAMINATIONS 1.0 PURPOSE This progedure describes the medical and bioassay examination required for TMI personnel prior to, during, and before termination of their employment.
2.0 DISCUSSION Medical examinations of radiation workers are presently only prescribed by regulation for reactor operators (see 3.0: References).
It is company policy that all Met Ed radiation workers receive periodic medical examinations as indicated in this procedure.
(A radiation worker is any person who could receive 300 mrem exposure in a i$4 quarter). These examinations are performed in order to ensure that no radiation related bodily changes go unnoticed, and that baseline data are available for evaluation of any accidental overexposures.
Bioassay examinations include whole body counting and radiobioassay of excreta. The bioassay program in force at TMI is based on the official guidelines contained in the AEC Regulatory Guides, Division 8: Occupational Health, and their supporting documents (see 3.0:
References).
Its main objectives are to ensure that personnel exposures are as low as practicable, to provide checks on the effectiveness of the radiation protection procedures, and to evaluate the radiological health status of personnel involved in uncontrolled j
incidents of exposure to radioactive materials.
1.0 197 081
1628 Revision 3 09/30/77 h0TE:
It must be understood that any of the following examinations (or other examinations not listed) may be performed when deemed advisable by the Radiation Protection Supervisor, Medical Consultant, cr Authoritative Management Official.
3.0 REFERENCES
3.1 With respect to medical examinations 3.1.1 Code of Federal Regulations, Title 10, Atomic Energy, Part 55:
Operator's Licenses, 5555.11 and 55.60.
3.1.2 Consultation with Radiation Management Corporation, Philadelphia, Penna.
3.2 With respect to bicassay examinations
- 3}
197 082 1.1
- e 1628 Revision 3 09/30/?7 3.2.1 NRC, Rcgulatory Guide 8.2:
Guide for Administrative Practices in Radiation Monitoring, February 2,1973.
=
3.2.2 American National Standards Institute, Standard ANSI N13.2 -
1969: Guide for Administrative Practices in Radiatire: Moni to ring.
3.2.3 NRC, Regulatory Guide 8.7: Occupational Radiation Exposure Records Systems, May 1973.
3.2.4 American National Standards Institute, Standard ANSI N13.6 -
1966Property "ANSI code" (as page type) with input value "ANSI N13.6 -</br></br>1966" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. (R1972): Radiation Exposure Records Systems.
3.2.5 NRC, Regulatory Guide 8.8:
Information Relevant to Maintaining Occupational Radiation Exposure as low as Practicable (Nuclear Reactors).
3.2.6 NRC, Regulatory Guide 8.9: Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program.
- aj
~
3.2.7 International Commission on Radiological Protection: Publications No. 2, 6, 9,10,10A and 12 (1959-1971).
3.2.8 Consultation with Radiation Managemer. Corporation, Philadelphia, Pennsylvania.
4.0 EQUIPMENT 4.1 Not applicable.
5.0 OPERATING PROCEDURES 5.1 Examinations to be performed before employment at TMI 5.1.1 Reactor operators and senior operators The initial and biennial medical examinations For reactor operators and senior operators are prescribed in Ref. 3.1.1.
5
~
If the last examination tefore employment at TMI has not included blood analysis, eye exaniination, and an evaluation of the hearing function, the operator will receive an ophthalmologic 197 08'
~
2.0
1628 Revision 3 examination with special reference to lens opacities and visual acuity (to be corrected before the employment), an audiometric investigation, and a complete blood cell count (with platelet count), hemoglobin, hematocrit and differential.
Bioassay examinat~:on will be as for other radiation workers.
- n a.
197 084 2.1
- _628 4/8/74 1
Revision 1
~
5.1.2 Other radiation workers Other radiation workers will receive a general medical examination including the hematological, audiometric and eye examinations as described in Section 5.1.1.
Bioassay examinations will include:
(a) Whole body count (all radiation workers)
(b) Tritium concentration in urine (for those radiation workers with previous exposure to tritiem in their work history).
(c) Total alpha activity in urine (for radiation workers previously exposed to alpha emitters).
If a whole body count cannot be performed before the start of their em-ployment, urine will be analyzed to determine the total beta activity and, in case the level exceeds 250 pCi/1, to determine the gamma spectral composition, and a whole body count performed as soon as possible after-2 wards.
NOTES:
1.
In this and following procedures, " urine means the total first morning voiding of urine.
2.
Recommended sensitivity for indicated analyses will be as given in Attachment 1 to these procedures.
5.1.3 Other TMI personnel All TMI non-radiation-wrkers receive a general medical examination before or as soon as possible after the start of their employment.
No special requirements (i.e. related to radiation protection) for this examination are needed.
If no previous exposure to radioactive products has occurred, this personnel
{
3 will not receive any bioassay examinations.
If such exposure has occurred, bicassay requirements are the same as those given for radiation workers (see 5.1.2).
5.2 Examinations to be performed during employment at TMI 197 085 5.2.1 Radiation workers 3.0
1628 08/20/75 Revision 2 All radiation workers receive a general medical examination every two years.
This examination wil' ine'ude blood analysis and audiometry as described in 5.1.1.
Ophthalmologic examination will include visual acuity checks and correction if necessary.
No slit lamp examination is indicated, except in those personnel over 50 years of age, and in those personnel who have pre-viously been exposed to neutron radiation with a total dose of 25 rems or more.
All radiation workers receive a whole body counting examins tion after re-fueling and/or as required. They submit urine for determinatier of. total beta activity about 6 months after the last whole body count.
If the total beta activity exceeds 250 pCi/1, the urine will be analyzed by gamma spectrometry.
5.2.2 Other personnel No special requirements for this category are necessary.
5.3 Special examinations (radiation workers only)
- 3j 5.3.1 After major maintenance outages and refueling all personnel involved will receive either a whole body count or radiobicassay of urine for total beta activity.
If possible, one of these examinations shall be timed to take place con-current with the annual bicassay examination described in 5.2.1.
5.3.2 Accidental exposures Actions required in case of accidental overexposures to radiation or radioactive materials shall be determined in consultation with Radiation Management Corporation, Philadelphia, Pennsylvania.
With respect to in-ternal contamination, actions to be taken shall depend on the body or organ burdens determined by whole body counting, and specifically, on.whether these
[>
internal burdens exceed appropriate action levels. The values for these levels are given in Attachment 2 to these procedures.
197 086 4.0
~
16g"n Revision 2 08/20/75 5.4 Examinations to be cerformed at termination of employment.
NOTE:
Examinations for employees terminating should be determined and scheduled in a timely manner upon the notification of the employee's in-tent to terminate.
Failure of the employee to comply with the requirements of this procedure will be so noted in the Employee's Personnel File.
5.4.1 Medical Examinations 1
=1 197 087 4,
1628 Revision 2 08/20/75 All TMI personnel shall receive a general medical examination prior to the termination of their employment.
For radiation workers, this examination shall include a blood analysis, audiometric and ophthalmologic examinations as described in 5.1.1.
5.4.2 Bioassay Examinations Non-radiation workers will not receive bioassay examinations unless there is reason to believe that they may have been exposed to radioactive materials during their employment.
"In this case a urinalysis for beta activity and a ganma spectral analysis of urine will be performed, further analysis and/or examinations may be performed if deemed necessary by the Radiation Protection Department."
Radiation workers will receive urinalysis for beta activity and a gamma spectral analysis of urine, further analysis and/or examinations may be
- 3 a a.3 performed if deemed necessary by the Radiation Protection Department.
.~
.I 197 088 5.0 i
_1,628 4/8/74 Revision 1
- to Recontended sensitivity for bicassay analyses PURPOSE The sensitivity recommended for bioassay analyses is based on the general require-ment that such analyses should indicate whether or not certain action levels have been exceeded.
REFERENCES See 3.2.6 and 3.2.7 of the procedures.
Recommended Minimum Detectable Levels (a) Urine, total beta activity The method employed should be capable of detecting a minimum level of 100 pCi/1 and allow the detection of 250 pCi/1 with a 95% Confidence Level not exceeding 25%.
(b) Urine, camma spectral analysis
_,y The method employed should be capable of detecting a minimum level of 100 pCi/1 of gamma emitting nuclides, assuming 100% yielu of gamma emission and Photon energies of 100 kev and greater.
(c) Urine, tritium concentration The minimum tritium concentration detectable by the method employed should be 5 nCi/1.
(d) Urine, " total alpha activity" The method employed should be capable of detecting a minimum of 0.025 pCi per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> urine portion of alpha emitters in the actinide series.
.~
l 197 089 6.0
1628 4/8/74 Revision 1
. Attachment 2 to Action levels for certain typical radionuclides encountered in nuclear power plant operations.
PURPOSE The action levels given in the table below indicate the limits of body burdens after single intakes of radioactive materials above which further investigation as to the internal dosimetry and biological significance shall be performed.
USE OF ACTION LEVELS The taole supplies two sets of figures: those applicable in case intake in the body is by inhalation of insoluble materiais, and those applicable in the event absorption of soluble materials into body fluids may be assumed to have occurred.
In the absence of sufficient information with respect to solubility and/or exact mode of intake, the first set of figures shall be used to determine the need for further investigation.
"Li I
- b 197 090 7.0
't.
11628 4/8/74 Revision 1 1
TABLE OF ACTION LEVELS (in units of nCi)
Lung Burden Body Burden (insoluble materials)
(soluble materials)
Nuclide days after intake 5 days after inhalation (1) 1 7
14 30 Cr-51 30,000 (2)
Mn-54 630 (2)
Fe-59 800 5,500 4,900 4,400 3,400 Co-58 800 70,000 25,000 14,600 4,100 Co-60 140 25,000 10,000 6,000 2,000 Zr/Nb-95 1,200 (2)
Ru-103 1,300 (2)
-(3) 300(4) 150 80 20 Cs-134 160 2,500 2,000 1,950 1,750 Cs-137
- 160 4,000 3,350 3,200 3,000 3$
Ba/La-140 600 8,000 5,400 4,700 4,000 Ce-141 3,000 18,500 15,700 12,500 5,500 Ce-144 100 300 290 285 275 NOTES:
(1) These amounts apply to radioactivity deposited in the pulmonary region of the lungs, i.e. those found in the total body at s5 days after the initial inhalation.
It may be assumed that the total body burden immediately after inhalation is approxicately 5 times higher than the amounts indicated.
For the period between 5 and 30 days af ter inhalation, the lung burden re-ductions are less than 20%.
(2) No data available.
(3) Cannot be assumed to be insoluble.
(4) Thyroid burden.
j 197 09' 8.0
- .