ML20002C634
| ML20002C634 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/25/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8101100627 | |
| Download: ML20002C634 (18) | |
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APR 2 51973 Doclet No. 50-155 l
Consumers Power Company ATTN:
Mr. Ralph B. Sewall Nuclear Licensing Administrator 212 West Michigan Avenue Jackson, Michigan 49201 Change No. 37 Gentlemen:
License No. DPR-6 Tour letter dated November 28, 1972, proposed changes to the Technical Specifica tion. of Facility License No. DPR-6.
Ibese proposed changes, submitted in response to our request dated September 28, 1972, add a section to the Big Rock Point Plant Technical Specifications entitled Plant Reporting Requirements.
During our review, we informed your staff that certain modifications and additions to the proposed changes were necessary to meet regulatory tequirements. These modifications have been made.
We have added a new Section 7.7, "Radiction and Eespiratory Protection Program" to your Technical Specifications. This specification super-sedes the letter of authorization issued May 19, 1966, which permitted ycu to make allowance for the use of respiratory protective equipment.
This new section reflects the current regulatory requirements relating to respiratory protective programs.
Based upor our review of your request, we have determined that the proposed changes, as modified, do not present significant hazards considerations not d.cribed or implicit ir. *.he Big Rock Point Safety Analysis Raport. There is reasonable asstrance that the health and safety of the public will not be endangered by operation in the manner proposed.
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UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. ?0545 APR 2 51973 Docket No. 50-155 Consumers Power Company ATIN:
Mr. Ralph B. Sewell Nuclear Licensing Administrator 212 West Michigan Avenue Jackson, Michigan 49201 Change No. 37 Gentlemen:
License No. DPR-6 Your letter dated November 28, 1972, proposed changes to the Technical
. Specifications of Facility License No. DPR-6.
These proposed changes, submitted in response to our request dated September 28, 1972, add a section to the Big Rock Point Plant Technical Specifications titled Plant Reporting Requirements.
During our review, we informed your staff that certain modifications and additions to the proposed changes were necessary to meet regulatory requirements. These modifications have been made.
We have added a new Section 7.7, " Radiation and Respiratory Protection Program" to your Technical Specifications.
This specification super-sedes the letter of authorization issued May 19, 1966, which permitted you to make allowance for the use of respiratory protective equipment.
This new section reflects the current regulatory requirements relating to respiratory protective programs.
Based upon our review of your request, we have determined that the proposed changes, as modified, do not present si uificant hazards t
considerations not described or implicit in the Big Rock Point Safety Analysis Report. Thure is reasonable assurance that the health and safety of the public will not be endangered by operation in the manner proposed.
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bco: w/cy 4/11/73 Mem ocket File to Fili AEC PDR Branch Reading RP Reading JRBuchanan WLaughlin EPA (3)
Consumers Power Company APli 11 73 AR R0 (3) occ JShea DLZiema m Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, Section 4.1.2.(b) of the Technical Specifiestf..s of Facility License No. DPR-6 is hereby changed to add the following underlined sentences batween the existing 6th and 7th sentences:
"(b) Operatinn Requirements The amargency condenser, core spray and backup core spray systems shall be operable and ready for service at all times during power operation. However, should one emergency condenser tube bundle develop a leak during power operation, it will be permissible to isolate the leak.ing tube bundle until the next outage. Soth bundles of the emergency condenser shall be available for service during cold to hot plant heat up for power production.
The core spray system...."
Sincerely.
Original Signed by:
Donald J. Skovholt Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing cc:
Mr. Paul A. Perry, Secretary TJCarter Consumers Power Con:pany NDube 212 West Michigan Avenue RMDiggs Jackson, Michigan 49201 Mr. Donald W. Aldrich Consumers Power Company D[AA Ie Legal Department 212 West Michigan Avenue UU
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4 APR 5 1973 Consumers Power Company 50, che Technical Accordingly, pursuant to Section 50.59 of 10 CF d as indicated in Att&chment A to this letter.
Sincerely,
- ggf, lt nald J ' kovho Assistant Director for Operating Reactors Directorate of Licensing
Enclosure:
Attachment A - Changes to Technical Specifications cc w/ enclosure:
Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue 49201 Jackson, Michigan Mr. Donald W. Aldrich Consumers Power Company Legal Department 212 West Michigan Avenue 49201 Jackson, Michigan l
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(ii) the method of shutting down the reactor (e.g., trip automatic rundown, or manually controlled deliberate shutdown);
(iii) duration of the outage; (iv) unit status during the outage (e.g.,
cold shutdown or hot shutdown); and (v) corrective action taken to prevent t
repetition, if appropriate.
(d) Maintenance A discussion of safety related maintenance (excluding preventative maintenance) performed during the reporting period on systems and components that are designated to prevent or mitigate the consequences of postulated accidents or to prevent the release of signifi-cant amounts of radioactive material.
Included in this category are systems and components which are part of the reactor coolant pressure boundary defined in 10 CFR 5 50.2(v), any part of the engineered saft?.y features or associated service and control systems that are required for the normal operation of engineered safety features, part of any reactor protection or shutdown system, or part of any radioactive waste treatment handling and disposal system or other system which may contain significant amounts of radioactive material. For any malfunctions for which corrective maintenance was required, information shall be provided on:
(i) the system or component involved; (ii) the cause of malfunction; (iii) the results and ef f ect on safe operation; (iv) corrective action taken to prevent repetition; and (v) precautions taken to provide for reactor safety dut r.g repair.
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k (e)
Changes, Tests, and Experiments A summary of all changes in the plant design and procedures that relate to the safe oper-ation of the plant shall be included in the Operations Summary section of these semi-annual reports. Changes, tests, and experi-ments performed during the reporting period that require authorization from the Commission pursuant to 10 CFR 50.59(a) are covered in paragraph 7.2.2.1.2(1)(a) of these Technical Specifications; however, those changes, tests, and experiments that do not require Commission authorization pursuant to 5 50.59(a) sic:1 be addressed.
The report shall include a brief description and the summary of the safety evaluation for those changes, tests, and experiments carried out without prior Commission approval, pursuant to the require-ments of 5 50.59(b) of the Commf usion's regulations, that 'The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the license, a report containing a brief description of such changes, tests, and axperiments, including a summary of the safety evaluation of each'.
(f) Radioactive Effluent Releases A statement of the quantities of radioactive effluents released from the plant, with data summarized on a monthly basis following the general format of Appendix A of USAEC Safety Guide 21.
(i)
Gaseous Effluents (a) Gross Radioactivity Releases (1) Total gross radioactivity (in curies), including noble j
and activation gases released.
(2) Maximum gro'ss radioactivity
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release rate during any one-hour period.
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I (3) Total gross radioactivity (in curies) by nuclide released, based on repre-sentative isotopic analyses performed.
(4) Percent of technical specifi-cation limit.
(b)
Iodine Releases (1)
Total iodine radioactivity (in curies) by nuclide released, based on repre-sentative isotopic analyses perfo rmed.
(2) Percent of technical specifi-cation limit for 1-131 released.
(c) Particulate Releases (1) Cross radioactivity (8,y) released (in curies) excluding background radio-activity.
(2) Cross alpha radioactivity released (in curies) excluding background radio-activity.
(3) Total gross radioactivity (in curies) of nuclides with half-lives greater than eight days.
(4) Percent of technical specifi-cation limit for particulate radioactivity with half-lives greater than eight days.
(ii)
Liquid Effluents (a) Gross radioactivity (8,y) released (in curies) excluding tritium and average concentration released to the unrestricted area.
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- (b) Total tritium and alpha radio-activity (in curies) released end average concentration released to the unrestricted area.
(c) Total dissolved gas radioactivity (in curies) and average concen-tration released to the unrestricted area.
(d) Total volure (in liters) of liquid waste released.
(e) Total volume (in liters) of dilution water used prior to release from the restricted area.
(f) The maximum concentration of gross radioactivity (8,y) released to the unrestricted area (averaged over the period of release).
(g) Total radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed.
(h) Percent of technical specification limit and 10 CFR Part 20 con-centration limits for unrestricted areas.
(iii) Solid Waste (a) The total amount of solid waste packaged (in cubic feet).
(b) The total estimated radioactivity (in curies) involved.
(c) Disposition, including dates and destination if shipped off site.
(g) Environmental Monitoring (i)
For each medium sampled; e.g.,
- air, sediment, surface water, soil, or fish, include:
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. (a) Number of sampling locations.
(b) Total number of samples.
(c) Number of locations at which levels are found to be signifi-cantly above local backgrounds.
(d) Highest, lowest, and the annual average concentrations or levels of raliation for the sampling point with the highest average and description of the location of that point with respect to the site.
(ii)
If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 1% of those that could result from continuous annual exposure to the concentration values listed in Appendix B, Table'II, Part 20, estimates of the likely resultant exposure to individuals and to population groups and assumptiens upon which estimates are based shall be provided.
(iii) If statistically significant variations of offsite environmental concentrations with time are observed, correlation of these results with effluent release shall be provided.
(h) Occupational Personnel Radiation Exposure A tabulation of personnel exposures shall be reported for the reporting period as follows:
less than 100 mrem, 100-500 mrem, 500-1250 mrem, 1250-2500 mrem, above 2500 mrem. Tabulate the number of personnel receiving more than 500 mrem exposure in the reporting period according to duty function; i.e.,
routine plant surveillance and inspection (regular duty), routine plant maintenance, special plant maintenance (describe maintenance), routine refueling oper-ation, special refueling operation (describe operation), and other job-related exposures.
Annually tabplate the number of personnel receiving more than 2500 mrem and report major cause(s).
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' 7.2.2.1.3 Nonroutine Reports a.
Reporting of Abnormal Events (1)
Abnormal Occurrence Reports Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Regional Regulatory Operations Office, with a copy to the Director of Licencing, followed by a written report within 10 days to the Director of Licensing (cc to the Director of the Regional Regulatory Operations Office) in the event of an abnormal occurrence. An abnormal occurrence is defined as any of the following:
(a) safety system setting less conservative a
than the limiting setting established in the Technical Specifications.
(b) Violation of a limiting condition for oper-ation established in the Technical Specifi-cations.
(c) An uncontrolled or unplanned release of radioactive material from any plant system designed to act as a boundary for such material in an amount of significance with respect to limits prescribed in Technical Specifications.
(d) Failure of one or more components of an engineered safety feature or plant protection system that causes or threatens to cause the feature or system to be incapable of performing its intended function.
(e) Abnormal degradation of one of the several boundaries designed to contain the radioactive materials resulting from the fission process.
(f) Significant uncontrolled or unanticipated changes in reactivity.
(g) Observed inadequacies in the implementation of administrative or procedgral controls such that the inadequacy causes' or threatens to cause the existence or development of an unsafe condition in connection with the operation of the plant.
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(h)
Conditions arising from natural or offsite manmade events that affect or threaten to affect the safe operation of the plant.
The written report on these abnormal occurrences and, to the extent possible, the preliminary telephone and telegraph notification shall (a) describe, analyze, and evaluate safety implications, (b) outline the measures taken to i
assure that the cause of the condition is determined, and (c) indicate the ccrrective action (including any changes made to the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems.
In addition, the written report shall relate any failures or degraded performance of systems and components for the incident to similar equipment failures that may have previously occurred at the plant. The evaluation of the saf ety implications of the incident should consider the cumulative experience obtained from the record of previous failures and malfunctions of the affected systems and components or of similar equipment.
b.
Reporting of Unusual Events A written report shall be forwarded within 30 days to the Director of Licensing and to the Director of the Regional Regulatory Operations Office in the event of:
(1)
Discovery of any substantial errors in the tran-sient or accident analysis or in the methods used for such analyses as described in the Final Hazards Summary Report or in the bases for the Technical Specifications.
(2)
Any substantial variance from perfctmance specifi-cations contained in the Technical Specifications or in the Final Hazards Summary Report.
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(3)
Any condition involving a possible single failure which, for a system designed against assumed single failures, could result in a loss of the capability of the system to perform its safety function.
c.
Startup Report A summary report of unit startup and power escalation testing and an evaluation of the results from such test programs shall be submitted following receipt of an operating license, following amendments to the licenses involving a planned increase in power level, following the installation of fuel that has a different design or was f abricated by a diff erent vendor, of following NSSS modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the facility.
The report shall include a comparison of sensured and predicted values and describe any corrective action taken to obtain acceptable operation. Startup reports shall be submitted within 90 d;ys following completion of startup test program or resumption of commercial power operation.
7.2.2.1.4 Special Reports Special reports shall be submitted in writing within 90 days to the Director of Licensing, USAEC, Washir.gton, D. C.
20545.
Special reports shall be submitted covering inspections, tests, and maintenance that are appropriate to assure safe operation of the plant. The frequency and content of these special reports are determined on an individual case basis and designated in these Technical Specifications.
Examples of subjects for such reports include:
a.
Authorization of changes, tests, and experiments in accordance with 10 CFR 50.59 analyzed as an unreviewed safety question.
b.
Containment leak rate tests.
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Inservice inspection reports, d.
Special maintenance reports.
e.
Radioactive effluent releases reports.
f.
Materials radiation surveillance specimens reports.
g.
Fuel performance following each refueling or partial refueling.
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In Section 7.0, add subsection 7.7, " Radiation Control and Respiratory Protection Program", as follows:
7.7 Radiation and Respiratory Protection Program 7.7.1 Radiation control procedures shall be maintained and made available to all station personnel. These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation pro-,
tection program shall be organized to meet the requirements of 10 CFR 20.
a.
Pursuant to 10 CFR 20.103(c)(1) and (3), allowance shall be made for the use of respiratory protective equipment in conjunction with activities authorized by the operating license for this plant in determining whether individuals in restricted areas are exposed to_ concentrations in excess of the limits specified in Appendix B, Table I, Column 1 of 10 CFR 20, subject to the following conditions and limitations.
(1) The limits provided in Section 20.103(a) and (b) shall not be exceeded.
(2)
If the radioactive material is of such form that intake through the skin or other additional route is likely, individual exposures to radioactive material shall be controlled so that the radioactive content of any critical organ from all routes of intake averaged over 7 consecutive days does not exceed that which would result from inhaling such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the pertinent concentration values pro-vided in Appendix B, Table I, Column 1 of 10 CFR 20.
(3) For radioactive materials designated "Sub" in the
" Isotope" column of Appendix B, Table I, Column 1 of 10 CFR 20, the concentration value specified shall be based upon exposure to the material as an external radiation source.
Individual exposures to these materials shall be accounted for as part of the limitation on individual dose in 5 20.101.
These materials shall be subject to applicable process and other engineering controls.
b.
In all operations in which adequate limitation of the inhalation of radioactive material by the use of process or other engineering controls is impracticable, the licensee shall permit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne radioactive material, provided:
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(1) The limits specified in paragraph a. above 6:e not exceeded.
(2) Respiratory protective equipment is selected and used so that the peak concentrations of airborne radio-active material inhaled by an individual wearing the equipment do not exceed the pertinent concentration values specified in Appendix B. Table I, Column 1 of 10 CFR 20. For the purposes of this subparagraph, the concentration of radioactive material that is inhaled when respirators are worn may be determined by dividing the ambient airborne concentration by the protection factor specified in Table 7.1 for the respir.ator protective equipment worn.
If the intake of radioactivity is later determined by other measure-ments to have been dif ferent than that initially estimated, the latar quantity shall be used in eval-uating the exposurea.
(3) The licensee advises each respirator user that he may leave the area at any time for relief from respirator use in case of equipment malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection afforded the wearer.
(4) The licensee maintains a respiratory prc'.ective program adequate to assure that the requirementa above are met and incorporates practices for respir atory protection consistent with those recommended by the American National Standards Institute (ANSI-Z88.2-1969). Such a program shall include:
(a) Air sampling and ot'.ner surveys sufficient to identify the hazard, to evaluate individual exposures, and to permit proper seleccion of respiratory protective equipment.
(b) Written procedures to assure proper selection, supervision, and training of personnel using such protective equipment.
(c) Written procedures to assure the adequate fitting of respirators and the testing of respiratory protective equipment for operability immediately prior to use.
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i I. (d) Written procedures for maintenance to assure full effectiveness of respiratory protective equipment, including issuance, cleaning and decontamination, inspection, repair, and storage.
(e) Written operational and administrative procedures for proper use of respiratory protective equip-including provisions for planned limitations
- ment, on working times as necessitated by operational conditions.
(f) Bioassays and/or whole body counts of individuals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection actually provided.
The licensee shall use equipment approved by the U. S.
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Bureau of Mines under its appropriate Approval Schedules as set forth in Table 7.1.
Equipment not approved under U. S. Bureau of Mines Approval Schedules shall be used only if the licensee has evaluated the equip-ment and can demonstrate by testing, or on the basis of reliable test information, that the material and performance characteristics of the equipment are at least equal to those afforded by U. S. Bureau of Mines approved equipment of the same type, as specified in Table 7.1.
(6) Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified in Table 7.1 i-selecting and using respiratory protective equipment.
These specifications with respect to the provisions of c.
5 20.103 shall be superseded by adoption of proposed changes to 10 CFR 20, Section 20.103, which would make this specification unnecessary.
I TABLE 7.1 PROTECTION FACTORS FOR RESPIRATORS I
PROTECTION FACTORS 2/
GUIDES TO SELECTION OF EQUIPMENT PARTICULATES BUREAU OF MINES APPRuv'i' SCllEDULES*
DESCRIPTION MODES AND VAPORS AND FOR EQUIPMENT CAPABLE OF PROVIDING AT CASES EXCEPT LEAST EQUIVALENT PROTECTION FACTORS TRITIUM OXIDE 3/
- or schedule superseding for equipment of type listed I.
AIR-PURIFYING RESPIRA'II)RS Facepiece, half-mask 4/ 7/
Facepiece, full 7/
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21B 30 CFR I 14.4(b)(4)
NP 100 21B 30 CFR I 14.4(b)(5); 14F 30 CFR 13
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ATMOSPHERE-SUPPLYING RESPIRATOR 1.
Airline Respirator Facupiece, hali,$sk CF 100 19B 30 CFR S 12.2(c)(2) Type C(i)
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Facepiece, full CF 1,000 19B 30 CFR s 12.2(c)(2) Type C(i)
.Facepiece, full 7/
D 100 19B 30 CFR g* 12.2(c)(2) Type C(ii)
Facepiece, full PD 1,000 19B 30 CFR s 12.2(c)(2) Type C(iii)
Hood CF 5/
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Suit CF 5/
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Self-Contain d Breathing Apparc.t.s (SLUBA) g acepiece, full 7/
2) 100 13E 30 CFR 011.4(b)(2)(1) v Ocepiece, full PD 1,000 13E 30 CFR s 11.4(b)(2)(ii) 1acepiece, full R
1,000 13E 30 CFR S 11.4 (b)(1)
M g III. COMBINATION RESPIRATOR Any co+'--tlon of air-Protection factor 19B CFR s,12.2(e) or applicable purifying and atmosphere-for type and mode scheduler as listed above supplying respirator of operation as listed above 1/, 2/, 3_/, 4/, 5,/, 6_/, 7/, (These notes are on the following pages)
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See the following symbols:
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CF: continuous flow D:
demand NP: negative pressure (i.e., negative phase during inhalation)
PD: pressure demand (i.e., always positive pressure)
PP: positive p.ressure R
recirculating (closed citcuit) 2/
(a) For purposes of this specification the protection factor is a measure of the degrce of protection afforded by a respirator, defined as the ratio of the concentration of airborne radioactive material outside the respiratory protective equipment to that in-side the equipment (usually inside the facepiece) under conditions of use.
It is applied to :he ambient airborne concentration to estimate the concentration inhaled by the wearer according to the following formula:
Concentration Inhaled = Ambient Airborne Concentration Protection Factor (b) The protection factors apply:
(1) only for trained individuals wearing properly fitted respir-ators used and maintained under supervision in a well-planned respiratory protective program.
(ii) for air-purifying respirators only when high efficiency (above 99.9% removal efficiency by U. S. Bureau of Mines type dioctyl phthalate (DOP) test) particulate filters and/or sorbents appropriate to the hazard are used in atmospheres not defi-cient in oxygen.
(iii)for atmosphere-supplying respirators only when supplied with adequate respirable air.
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Excluding radioactive contaminants that present an absorption or sub-mersion hazard. For tritium oxide approximately half of the intake occurs by absorption through the skin so that an overall protection factor of not more than approximately 2 is appropriate whea atmosphere-supplying respirators are used to protect against tritium oxide. Air-purifying respirators are not recom= ended for use a3ainst tritium oxide.
See also footnote 5/, below, concerning supplied-air suit. and hoods.
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Under chin type only. Not recommended for use where it m.ght be pos-sible for the ambient airborne concentration to reach ins antaneous values greater than 50 times the pertinent values in Apper lix B, Table I, Colu=n 1 of 10 CFR, Part 20.
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Appropriate protection factors must be determined taking t: count of the design of the suit or hood and its permeability to the cor taminaat under conditions of use. No protection factor greater the - 1,000 shall be used except as authorized by the Co= mission.
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No approval schedules _ currently ava:lable for this equipment. Equipment must be evaluated by testing or on '> asis of available test information.
7f Only for shaven faces.
NOTE 1 Protection factors for respirators, as may be approved by the U. S. Bureau of Mines according to approv.s.1 schedules for respirators to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection fac-tors listed in this Table. The protection factors in this Table may not be appropriate to circumstances where chemical or other respiratory hazards exist in addition to radioactive hazards. The selection and use of respirators for such cir-cumstances should take into account approvals of the U. S.
Bureau of Mines in accordance with its applicable schedules.
NOTE 2:
Radioactive contaminants for which the concentration values in Appendix B. Table I of 10 CFR Part 20 are based on internal dose due to inhalation may, in addition, present externci exposure hazards at higher concentrations.
Under such cir-cumstances, limitations on occupancy may have to be governed by external dose limits.
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