ML19326C171

Revised Proposed Tech Specs 6.0-6.11 Re Administrative Control for Facility

ML19326C171
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/30/1976
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326C167	List: ML19326C166 ML19326C171
References
NUDOCS 8004210667
Download: ML19326C171 (2)

Text

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Superintendent of Power Plant shall be responsible for overall facility operation.

In his absence, the Assistant Superintendent of Power Plant shall assume all responsibility and perform all duties of the Superintendent of Power Plant.

If both the Super-intendent of Power Plant and his assistant are absent, these respon-sibilities and duties are assumed by the Supervisor of Plant Operations followed by the Technical Support Engineer.

6.2 ORGANI2ATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

rACILITY STAFF 6.2.2 The Facility organi:ation shall be as shown on Figure 6.2-2A and 6.2-2B and each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the IIcalth Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING l

6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Supervisor of Plant Operations and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function r

6.S.I.1 The Plant Safety Committee shall function to advise the Super-intendent of Power Plant on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:

8004210

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s 0

TABLE 6.2-1 ARKANSAS NUCLEAR ONE MINIMUM Sil!FT CREW COMPOSITION #

UNIT 1 LICENSE COLD AND REFUELING CATEG0RY ABOVE COLD SIIUTDOWN S!!UTDOWNS SOL 1

1*

OL 2

1 NON-LICENSED 2

1

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling, supervising refueling operations after the initial fuel loading.

1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

Additional Requirements:

1.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

2.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

3.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

4.

All refueling operations after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling who has no other concurrent responsibilities during this operation.

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l SENIOR VICE PRESIDENT PROD.,TRANS.

8 ENGRG.

SAFETY REVIEW E

CUALITY ASSURANCE COMMITTEE E

COMMITTEE DIRECTOR POWER PRODUCTION I

ASST. DIRECTOR POWER PRODUCTION MANAGER MANAGER MAHACER g

OVALITY NUCLEAR NUCLEAR LICENSING ASSURANCE PROJECTS FUEL SUPERINTENDENT COMMITTEE ARKANSAS POWER G LIG!!T C05tPANY FIGURE ARKANSAS NUCLEAR ONE - UNIT 1 IANAGEFfENT ORGANIZATION CIIART 6.2-1

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SUPERINTENDENT OF PowC9 PLANT CE AS$1ST ANT SUPT OF P0wCR PL ANT CE L50 SEE FIGURE 6.2-2B I

l l

TEC C

S ORT g gg

'UPVSR-PLNT OPS

0. C. EmetNEER CE LSO l

i I

I I

OW 8 # 8" CHEwa ENV H. P.

PERF0*W ASST.SUPv3R PLT QP Q.C INSPEC TORS SUPVSR SUPVSR ENON.

LSO ASST H P SHIPT OPOUPVSR SUPVSR LSO PL AN T OPER j

LO CADIO CLN. L A 8.

CHEutSTS CHEMISTS H. P.'s ASST PLNT OPER LO WSTd.

CONT.

i CPER.

C Degree or Equivalent Required AUX.

CC - Inqineering Degree or (qutvalent c quicc.:

e L30 - Senior Opera *nr Literse Required LO Operator Liccase Required l

ARKANSAS 00NER 4 LICifT CO.

FUNCTIONAL ARKA.NSAS NUCLEAR ONE-UNIT 1 ORCANI.'.ATION FOR FIGURE PLA.NT OPERATION 6.2 2A

. ))p 7

" ' ~ ~ -

SEE FIGURE 6.2-2A 4

I I

l SUPVSR*PLNT MAINT NUCLEAR EN44.

INST NE CE S

SR I

CE I

I I

I ASST WAaNT SUPVSR REAC704 REACTOR ASST lac ENOR.

TECH.

SUPVSR

__ C E PLNT.WAlstf.

PL AN T ELECTN.

REPRuN IaC TECH

~

C Degree or Eculvalent Requiree CI - Engineering Degree or Equivatert Rcriuirc4:

l 1

L50 Senior Operator License Requirci LO - Operator License Requ6 red l

I ARKANSAS Poh!.R 6 LICliT CO.

FUNCTIONAL ARKANSAS _ NUCLEAR ONr.-UN'IT 1 ORGANI'.ATION FOR FIGURE PLANT OPEPATION 6.2 2B

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l Chairman:

Assistant Superintendent of Power Plant Member:

Technical Support Engineer Member:

Instrumentation 6 Controls Supervisor Member:

Supervisor of Plant Operations Member:

Supervisor of Plant Maintenance Member:

Nu:1 car Engineer Member:

!!calth Physics Supervisor 4

The Superintendent of Power Plant shall appoint an acting chair-man in the absence of the Assistant Superintendent of Power Plant.

ALTERNATES 6.5.1.3 Alternate members shall be appointed by the PSC Chairman to serve on a temporary basis: however, no more than two alternates shall participate as voting members in PSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PSC shall meet at Icast once per calendar month and as con-vened by the PSC Chairman or his designated alternate.

QUORIEl 6.5.1.5 A quorum of the PSC shall consist of the chairman and three members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:

Review of 1) all procedures required by Specification 6.8 a.

and revisions thereto, 2) any other proposed procedures or revisions thereto as determined by the Superintendent of Power Plant to affect nuclear safety.

b.

Review of all proposed tc<ts and experiments that affect nuclear safety.

Review of all proposed changes to the Appendix "A" Tech-c.

gical Specifications, d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications c.

including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrer.ce to the Superintendent of Power Plant, f.

Review of those Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification of the Commission.

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g.

Review of facility operations to detect potential nuclear safety hazards.

h.

Performance of special reviews and investigations and reports thereon as requested by the Superintendent of Power Plant.

i.

Review of the Plant Security Plan and implementing procedures and shall subr.it recommended changes to the Superintendent of Power Plant.

j.

Review of the Emergency Plan and impicmenting procedures and shall submit recommended changes to the Superintendent of Power Plant.

AUrl10RITY 6.5.1.7.1 The Plant Safety Committee shall:

a.

Recommend to the Superintendent of Power Plant written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.

6. 5.1. 7. 2 In the event of a disagreement between the recommendations of the Plant Safety Connittee and the actions contemplated by the Superintendent, the course determined by the Superinten-dent to be more conservative will be followed.

Records of 1

the disagreement will be sent for review to the Assistant

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Director, Power Production and the Chairman of the Safety Review Committee by the Superintendent on the next working day.

RECORDS 6.5.1.8 The Plant Safety Committee shall maintain written minutes of each meeting and copies shall be provided to the Chairman of the Safety Review Committee by the Superintendent of Power Plant.

6.5.2 Safety Review Committee (SRC)

FUNCTION 6.5.2.1 The Safety Review Committee shall Se c-; oc :o provide independent review and audit of designated ac';r '.

t the areas of:

a.

nuclear power plant operations b.

nuclear engineering

.c.- - chemistry and radiochemistry

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d.

metallurgy

c. -instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

environmental considerations 1.

other appropriate fields required by the unique characteristics of the nuclear power plant COMPOSITION

6. 5 ~. 2. 2 The SRC shall be composed of the:

Chairman: Director Power Production Member:

Asst. Director, Power Production Member:

Maintenance and Operations Coordinator Member:

Manager of Safety Member:

Arkansas Nuclear One Superintendent of Power Plant Member.

Representative from G.O. Chemistry Section Member:

Arkansas Nuclear One Nuclear Engineer Member:

Manager, Nuclear Fuel Member:

Radiation and Health Physics Consultant Member:

Nuclear Safety Consultant Member:

Manager, Licensing In his absence, the Chairman shall appoint an Acting Chairman.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates.shall participate as voting members in SRC activities at any one time.

CONSULTANTS -

6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.

FEETING FREQUENCY 6.5.2.5 The SRC shall meet at Icast once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereaf ter.

QUORUM

~6.5.2.6 A quorum of SRC shall consist of the Chairman or his designated alternate and five members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

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REVIEW.

6.5.2.7 The SRC shall review:

a.

The safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unrevic+;cd safety question as defined in Section 50.59, 10 CFR.

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or licenses, c.

Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuc1bar

safety, g.

Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.

h.

Reports and meeting minutes of the PSC.

AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a.

The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.

b.

The performance and retraining of all members of the facility management and operations staff, and the performance, training, and qualifications-of new members of the entire facility staff at least once per year.

c.

The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.

d.

The Facility Emergency Plan and implementing procedures at least once per two years.

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m e.. The Facility Security Plan and implementing procedures at 1 east once per two years, f.

Any other area of facility operation considered appropriate

'by the SRC or the t;nior Vice President (PT6E)

AUT110RITY 6.5.2.9 The SRC shall. report to and advise the Senior.Vice President (PT6E) on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and dis-tributed as indicated below:

a.

Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice President (PT6E) within 30 days following each-meeting, b.

Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved and forwarded to the Senior Vice President (PT6E) within 30 days following completion of the review, c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President (PT6E) and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for Reportable Occurrences:

a.

The_ Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.

b.

Each Reportable Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PSC_and submitted to SRC, the Assistant Director, Power Production by the Superin--

tendent of Power Plant.

6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least hot shutdown within one hour.

b.

The Nuclear Regulatory Commission shall be notified and a report _ submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.12.3.1 l

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6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below,

, Administrative, Quality Control and Security procedures covering a,

the control of equipment, personnel, records, and activities -

within the plant.

b.

General plant operating procedures covering the normal startup, operation and shutdown of the reactor and operation of all systems and components involving nuclear safety of the facility, Procedures for correcting abnormal, off-normal or alarm conditions, c.

which affect nuclear safety.

d.

Procedures for combating emergencies.

Procedures for li;niting personnel exposure to radioactivity, c.

f.

Procedures for control, calibration and adjustment of tools, gauges, instruments, controls and other measuring and testing devices important to nuclear safety.

g.

Procedures for surveillance and test activities of equipment required by the Appendix A Technical Specifications.

h.

Procedures for refueling operations.

i. Procedures for performing maintenance which can affect the performance of safety related equipment.

j. Procedures for chemical and radiochemical cc7 trol.

6.3.2 All procedures described in 6.8.1 above, and changes thereto (except editorial and typographical changes), shall be reviewed by the Superintendent prior to implementation, except as provided in 6.8.3 below.

6.S.3 Temporary _ changes to procedures in 6.8.1 above, which do not change the intent of.the original procedure may be made, provided such changes are approved by two members of the plant staff, at least one of whom shall be a Licensed Senior Operator. Temporary changes which may affect the intent of the original procedure may be made, provided such changes are approved by the Superintendent of Power Plant. Temporary changes shall be reviewed by the Plant Safety

- Committee at the next month's scheduled meeting.

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- 6.9 RECORD RETEEION 6.9.1 The following records shall be retained for at least five years:

a.

Records and logs of facility operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

All Reportable Occurrences submitted to the Commission pursuant c.

to ' Specification 6.12.3.

d.

Records of surveillance activities, inspections and calibrations required by the Appendix A Technical Specifications.

Records of reactor tests and experiments.

e.

f.

Records of changes made to procedures required by Specifi-cation 6.8.1 g.

Records of radioactive shipments.

~ h.

Records of sealed source leak tests and results.

i.

Records of annual physical inventory of all source material of record.

6.9.2 The following records shall be retained for the duration of the Facility Operating License:

Records and drawing changes reficcting facility design modifi-a.

cations made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, Records of facility radiation and contamination surveys.

c.

d.

Records of radiation exposure for all individuals entering radiation control areas.

Records of gaseous and liquid radioactive material released c.

to the environs.

f.

Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

g.

Records of training and qualification for current members of the plant staff.

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h.

Records of in-service inspections performed pursuant to these Technical Specifications.

1.

Records of Quality Assurance activities required by Section 17 of the Quality Assurance Manual for Operations.

j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PSC and the SRC.

6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radi-ation exposure.

6.11 RESPORATORY PROTECTION PROGRAM ALLOWANCE 6.11.1 Pursuant to 10 CFR 20.103(c)(1) and (3); allowance may be made

-for the use of respiratory protective equipment in conjunction with activities authori:cd by the operating license for this facility 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 limitation, a.

The limits provided in Section 20.103)a) and (b) shall not be exceeded.

b.

If the radioactive material is of such form that intake through the skin or other additional route is likely, individual expo-sures 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 provided in Appendix B, Table I, Column 1, of 10 CFR 20, c.

For radioactive materials designated "Sub" in the " Isotope" column of Appendix B,~

Tabic '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 expo-sures to these materials shall be accounted for as part of the limitation on individual dose in 520.101. - These materials shall be subject to applicable process and other engineering controls.

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,..s PROTECTION PROGRAM 15. 1 1. 2 In all operations in which adequate limitation of the inhalation of radioactive material by the use of process or other engineering controls is impracticabic, the licensee may permit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne radioactive material, provided:

a.

The limits specified in 6.11.1 above, are'not exceeded.

b.

Respiratory protective equipment is selected and used so that the peak concentrations of airborne radioactive material inhaled by an individual wearing the equipment do not exceed the pertinent concentration values specified in Appendix B, Table 1, Column 1, of 10 CFR 20.

For the purposes of this subparagraph, the con-t centration of radioactive material that is inhaled when respir-ators are worn may be determined by dividing the ambient airborne concentration by the protection factor specified in Table 6.11-1 for the respirator protective equipment worn.

If the intake of radioactivity is later determined by other measurements to have been different than that initially estimated, the later quantity shall be used in evaluating the exposure.

The licensee advises each respirator user that he may leave the c.

area at any time for relief from respirator use in case of equip-ment malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection afforded the wearer.

d.

The licensee maintains a respiratory protective program adequate to assure that the requirements above are met and incorporates practices for respiratory protection consistent with those recommended by the American National Standards Institute (ANSI-Z88.2-196o). Such'a program shall include:

1.

Air sampling and other surveys sufficient to identify the hazard, to evaluate individual exposures, and to permit proper selection of respiratory protective equipment.

2.

Written procedures to assure proper selection, supervision, and training of personnel using such protective equipment.

3.

Written procedures to assure the adequate fitting of respirators; and the testing of respiratory protective equipment for operability immediately prior to use.

4.. Written procedures for maintenance to assure full effective-ness of respiratory protective equipment, including issuance, c1 caning and decontamination, inspection, repair, and storage.

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e, 5.

Written operational and administrative procedures for proper use of respiratory protective equipment including provisions for planned limitations on working times as necessitated by operational conditions.

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6.

Bioassays and/or whole body counts of individuals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection actually proVided, c.

The licensee shall use equipment approved by the U.S. Bureau of Mines under its appropriate Approval Schedules as set forth in Tabic 6.11-1.. Equipment not -approved under U.S. Bureau of Mines Approval Schedules shall be used only if the licensee has evaluated the equipment and can demonstrate by testing, or on the basis of reliable test information, that the material and performanace 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 6.1*.1.

f.

Unless otherwise authorized by the Commission, the licensee shall not assign protection factors in excess of those specified in Table 6.11-1 in selecting and using respiratory protective equipment.

REVOCATION 6.11.3 The specifications of Section 6.11 shall be revoked in their entirety upon adoption of Jhe proposed change to 10 CFR 20, Section 20.103, which would make such provisions unnecessary.

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TABLE 6.11-1 PROTECTION FACTORS FOR RESPIRATORS PROTECTION FACTORS 2/

GUIDES TO SELECTION OF EQUIPMENT PARTICULATES AND BUREAU OF MINES / NATIONAL INSTI'lVTE

. VAPORS AND CASES FOR OCCUPATIONAL SAFETY AND llEALTil EXCEPT TRITIUM APPROVALS DESCRIPTION.

MODES 1/~

OXIDE 3/

I.

AIR-PURIFYING RESPIRATORS'

' Facepiece,. half-mask 4/,

7/

NP.

.5 30 CFR Part 11 Subpart K-4 Facepiece, full 7/

NP 100 30 CFR Part 11 Subpart K

.)

II.

ATFK)SPilFRE-SUPP LYING RESPIRATOR 1.

Airline respirator s

[

Facepiece, llalf-mask CF

'100 30 CFR Part 11 Subpart J Facepiece,' Full CF' 1,000 30 CFR Part 11 Subpart J Facepiece, Full 7,/

D 100 30 CFR Part 11 Subpart J Facepiece, Full PD 1,000 30 CFR Part 11 Subpart J liood CF 5/

30 CFR Part 11 Subpart J Suit CF 5/

6/

2.

Self-contained breathing apparatus (SCBA)

Facepiece, Full 7/

D-100 30 CFR Part 11 Subpart 11 Facepiece, Full PD 1,000 30 CFR Part 11 Subpart 11 Facepiece, Full R

100 30 CFR Part 11 Subpart il F

III. COMBINATION RESPIRATOR I'

Any combination of air-Protection factor for purifying and atmosphere-type and mode of opera-30 CFR Part 11 ll.63(b) supplying respirator

. tion as listed above.

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' TABLE 6.11-1 NOTES

1/ See ' the followind symbols

CF: Continuous Flow D: ; Demand NP: Negative fressure (i.e., negative phase during inhal'ation)

PD: ; Pressure Demand (i.e., always positive pressure) s R: Recirculating (closed circuit) 2/, (a) For purposes of this. specification-the protection factor is a measure of the : degree of protection afforded by a respirator,

? defined as the ratio of the' concentration of-airborne radio-

-active material outside the respiratory protective equipment to that inside the equipment (usually inside the facepiece) under conditions of use.

It is applied'to the ambient. air-borne concentration to estimate the concentration inhaled by

.the wearer according to the following formula:

1 Concentration Inhaled = Ambient Airborne Concentration Protection Factor (b) The protection factors apply:

i (i)- only for trained individuals wearing properly fitted respirators usad and maintained under supervision in s

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) par-iculate filters and/or sorbents appropriate to the hazard are used in g

atmospheres not deficient in oxygen.

(iii) for atmosphere-suppl ~ing respiratcr's only when supplied with adequate respire le air.

3/

Excluding radioactive contaminar.ts that present an absorption or submersionihazard. For tritium oxide approximately half of the in-take occurs by absorption through the skin so that an overall pro-tection factor. of not more than approximately 2 is appropriate when atmosphere-supplying respirators are used to protect against tritium. oxide. Air-purifying' respirators are not recommended for use against tritium oxide. See also footnote 5/, below, concerning supplied-air suits and hoods.

. h/ Under-~chinLtype only..Not recommended for use where it might be possibleEror the ambient,nirborne-concentration to reach instanta-neous values greater'than 50 times'the pertinent values in Appendix B, Table I,: Column-1 of 10 CFR 20.

1

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5/ Appropriate protection factors must be determined taking account of the designL of the suit for hood and its permeability to the. contaminant

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under conditions of use. No protection factor greater than 1,000 shall be used except as authorized by the Commission.

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6/ No approva11 schedules currently available for this equipment.

Equip-ment must be evaluated by-testing or on basis of available test

' in fo rmation '.

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7/ Only for shaven faces.

NOTE 1: Protection factors for respirators, as may be approved by the U. S. Bureau of Mines or the National Institute for Occupational Safety and Health according to approval schedules for respirators to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors listed in this Table.

The protection factors in this 1

Table may not be appropriate to circumstances where chemical or other respiratory hazards exist in addition to radtoactive hazards.. The selection and use of respirators for such circumstances should take into account approvals of the U. S.

Bureau of Mines or the National Institute for Occupational Safety and Health in accordance with its applicable schedules.

NOTE 2: Radioactive contaminants for which -the concentration values in Appendix B, Table I of 10 CFRlpart 20 are based on internal dose due to inhalation may, in addition, present external exposure ha:ards at higher concentrations. Under such circumstances, limitations on occupancy may have to be govern-ed by external dose limits.

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