ML20002A478

Amend 45 to License DPR-3,deleting Tech Specs Requirements for Submittal of Annual Operating Rept

ML20002A478
Person / Time
Site:	Yankee Rowe
Issue date:	02/22/1978
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20002A477	List: ML20002A476 ML20002A478 ML20002A479 ML20002A480
References
NUDOCS 8011170328
Download: ML20002A478 (18)

Text

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NUCLEAR REGULATORY COMMisslON 3

g WASHING TON. D. C. 20555 h%

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YANKEE ATOMIC ELECTRIC COMPANY _

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DOCKET N0. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)

}.j AMENDMENT TO FACILITY OPERATING LICENSE

Ji Amendment No.45 License No. OPR-3 7p.

1.

The Nuclear _ Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Yankee Atomic Electric Company (the licensee) dated October 31, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the-Comission's rules and regulations g~.y set forth in 10 CFR Chapter I-B.

The facility v 'll operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and_ safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to tF.e health and safety of the public; E.

The issuance of this amenduent is in accordance with 10 CFR Part 51'of.the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications-as' indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating Licen'se No.

DPL' is hereby amended to read as follows:

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9 (2) _ Technical Spectfications -

The Technical Specifications contained in Appendix A, as revised through Amendment tio. 45, are hereby incorporated

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in the-license.. The licensee shall operate the facility E.U.e in accordance with the Technical Specifications.

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This lic'ense' amendment is-effective as of the date of its issuance.

.=i FOR THE NU LEAR REGULATORY C0!NISSION ht()ddh' A. Schwencer, Chief

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Operating Reactors Branch #1

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Division of Operating' Reactors

Attachment:

Changes to the Technical Specifica tions '

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Date of Issuance: February 22, 1978

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ATTACHMENT-TO LICENSE AMENDMENT NO. 45 5

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Revise Appendix A as follows:

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Remove the following pages.and insert revised pages:

6 6-16 6 C-18

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6 6-20 6 6-22

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6 6 = riE 6 6-26 4

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6-29 Marginal /@es i'ndicate revised area. Overleaf pages are provided for convenientie.

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ADMINISTRATIVE CONTROLS s:. r l'h;:

Startup reports shall be submitted within (1) 90 days following com-s.

pletion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 mcnths following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

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6.9.2 Annual Report. Annual reports covering the activities of the unit f

as described below for the previous calendar year shall be submitted

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prior to March 1 of each year.

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Reports required on an annual basis shall include:

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A tabulation on an annual basis of the number of station.

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utility and other personnel (including contractors) receiving i -

exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,(a) e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste i

processing, and refueling. The dose assignment to various duty F

functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than e

205 of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the whole body dose received from external sources shall be assigned to specific major work functions.

b.

Any other unit unique reprts required on an annual basis.

6.9.3 Monthly Operatina iie' port.

Routine reports of ooeratina statistics ano shutdown experience shall be submitted on a monthly basis to the l

Director, Office of Management Information and Program Control U. S.

Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to L

i the approoriate Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.

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(a)This tabulation supplements the requirements of 5 20.407 of 10 CFR l

Part 20.

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6-15 Amendment No. 45 YANKEE-ROWE

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ADMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES

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6.9.4 REPORTABLE OCCURRENCES, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report be made to the original report date.

shall be completed and reference she'1 Prompt Notification With Written Followup. The types of a.

events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and confirmed Ly telegraph, mailgram, or facsimile transmission to the Director E

of the appropriate Regional Office, or his designate no later than the first working day following the event, with a w*itten followup report within two weeks. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.

Infomation provided on the licensee avent

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report form shall be supplemented, as needed, by additior.a1

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narrative material to provide a complete explanation of the circumstances surrounding the event.

(1) Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications or failure to complete the required protective function.

Note:

Instrument drift discovered as a result of testing need not be reported under this item but may be reportable underitemsa(5),a(6), orb (1)below.

(2) Operation of the unit or affected systems when ar; param-eter or operation subject to a limiting condition is less conservative than the least conservative aspect of the limiting condition.for operation established in the Technical-Specifications.

If specified action is taken when a system is found to Note:

be operating between the most conservative and the least conservative aspects of a limiting condition for opera-tion listed in the Technical Specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item b(2) below.

d (3) Abnormal degration discovered in fuel cladding, reactor coolant pressure boundary, or. primary containment.

.ly Amendment No. 45 YANKEE-ROWE 6-16

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Note: Leakage of valve packing or gaskets within the limits E= =

for IDENTIFIED LEAKAGE set forth in Technical Speci-fications need not be reported under this iten.'

(4) Reactivity anomalies, involving disagreement with the

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predicted value of reactivity balance under steady state

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w conditions during power operation, greater than or equal to 1% ak/k;' a calculated reactivity balance indicating a shutdown margin less conservative than specified in the 5

technical specifications; short-term reactivity increases E

that correspond to a reactor period of less than 5 seconds or, if sub-critical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any,/nplanned criticality.

(5) Failure or malfunction of one or more components which

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prevents or could prevent, by itself, the fulfillment of e

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the functional requirements of system (s) used to cope f T with accidents analyzed in the FHSR.

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(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the FHSR.

f Note: For items a(5) and a(6), reduced redundancy that b

does not result in a loss of system function need not be reported under this section but may be reportable under items b(2) and b(3) below.

(7) Conditions arising from natural or man-made events that.

as a direct result of the event require plant shutdown, cperation of safety systems, or other protective neasures required by technical specifications.

(8) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the FHSR or in the Bases for ti.J Technical Specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

.1 (9) Performance of structures, systems, or components that requires remedial action or corrective measures to pre-vent operation in a manner less conservative than assamed in the accident analyses in the FHSR or Technical Specifica-

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tions Bases; or discovery during plant life of conditions not specifically cor.sidered in the FHSR or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of unsafe conditions.

YANKEE-ROWE.

6-17 Amer.dment No. 45

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ADMINISTRATIVE CONTROLS This item is intended to provide for reporting of Note:

potentially generic problems.

The REPORTABLE OCCURRENCES dis-Thirty Day Written Reports.

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~ cussed below shall be the subject of written reports to the Director of the ap3ropirate Regional Office within thirty days of occurrence of tie event. The written report shall include, as a minimum, a completed copy of a licensee event report Information provided on the licensee event report form form.

shall be supplemented, as needed, by assitional narrative material 6 provide complete explanation of the circumstances surrounding the event.

(1) Reactor protection system or engineered safety feature instrument settings which are found to be less conser-vative than those established by the Technical Specifi-cations but which do not prevent the fulfillment of the functional requirements of affected systems.

(2) Conditions leading to operation in a degraded mode per-mitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items b(1) and b(2) need not be reported except where test results them-selves reveal a degraded node as described above.

(3) Observed inadequacies in the implementation of admin-istrative or procedural controls which threaten to cause

r. eduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

(4) Abnormal degradation of systems other than those specified in item a(3) above designed to contain radioactive material resulting from the fission process.

Sealed sources or calibration sources are not included Note:

under this item.

Leakage of valve packing or gaskets within the limits for IDENTIFIED LEAKAGE set forth in Technical Specifications need not be reported under this item.

6.9.5 Unique Reporting Requirements Environmental Radiological Monitoring a.

YANKEE-ROWE 6-is Amendment No. 45 y

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ADMINISTRATIVE CONTROLS A report on the Environmental Radiological Monitoring Program for the previous twelve months of operation shall be submitted

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(1) For each medium sampled during the reporting period,

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e.g., air, baybottom, surface water, soil, fish; include:

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.i (a) Number of sampling locations, (b) Total number of samples,

$g (c) Number of locations at which levels are found to te k

significantly above local backgrounds, and

'-s (d) Highest, lowest, and average concentrations or levels of radiation for the sampling point with the highest average and description of the location of

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that point with respect to the site.

(2)

If levels of radioactive materials in environmer.tal media as determined by an environmental monitoring program indicate the likelihood of public intakes in excess of 1*4 of those that could result from continuous 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 assumptions upon which estimates are based shall be provided.

(3)

If statistically significant variations of offsite environ-mental concentrations with time are observed, correlation of.these results with effluent release shall be provided.

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.b.

Semiannual Effluent Release Report Within 60 days after January 1 and July 1 of each year a report shall be submitted covering the radioactive content of effluents released to unrestricted areas during the previous six months of operation. The data shall be summarized on a monthly basis and included as a minimum:

(1) Gaseous Effluents (a) Gross Radioactivity Releases (i) Total gross radioactivity (in curies), primarily noble and activation gases.

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(ii) Maximum gross radioactivity release rate during any one-hour period.

(iii) Total gross radioactivity (in curies) by nuclide

.fM released based on representative isotopic

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analyses performed.

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(iv) Percent of Technical Specification limit.

(b) Iodine Release _

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(1) Total-iodine-radioactivity (in curies) by nuclide released based on representative isotopic analyses perfonned.

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(c) Particulate Releases N

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Total gross radioactivity (8,y) released (in curies) excluding background radioactivity.

(ii) Gross alpha radioactivity release'd (in curies) excluding background radioactivity.

(iii) Total gross radioactivity (in curies) of

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N nuclides with half-lives greater than 8 days.

(iv) Percent of Technical Specification' limits for particulate radioactivity with half-lives greater than 8 days.

~N, (2) Liquid Effluents (a) Total gross radioacti;ity (s.y) released (in curies) excluding tritium and average concentration re: eased to the unrestricted area.

(b) The maximum wncentration of gross radioactivity (8,y) released to the unrestricted area (averaged

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over the period of release).

(c) Total tritium and total alnha radioactivity (in curies)

~F released and average concentration released to the unrestricted area.

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YANKEE-ROWE 6-20 Amendment No. 45 h

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ADMINISTRATIVE CONTROLS

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Total dissolved gas radioactivity (in curies) and (d) '~ average concentration released to the unrestricted area.

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. (e), Total volume -(in. liters) of.. liquid waste released.

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e s:t (f) Total volume (in liters) of dilution water used prior reE2

to release from the restricted area.

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(g) Total gross radioactivity-(in curies) by nuclide i:2...:._

-released based on representative isotopic analyses

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(h). Percent of Technical Specification limit for total R.dd:

radioactivity.

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. (3) Solid Wastes d].5.:..

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- (a) The total amount of. solid waste shipped (in cubic feet).

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(b) The total ' estimated radioactivity (in curies) involved.

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' (c)' Dispositi.on including date and destination.

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6.9.6 Special reports shall be sutoitted to the' Director of the Office

}n of Inspection and Enforcement Regional Office within tne tirie period r:..z

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f specified for'each report.

These reports shall be submitted covering L."

the. activities identified below pursuant to the requirements of the i

applicable reference specification:

N a.

Inservice Inspection Program Reviews, Specification 4.4.9.1.

4 b.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

c..

Inoperable Meteorological Monitoring Instrumentation, Specifi-catien 3.3.3.3.

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Sealed Source leakage in excess of limits, Specification 4.7.6.3.

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Radioactive Solid Waste Disposal, Specification 3.7.9.1.

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i YANKEE-ROUE 6-21 Amendment No. 45

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6.10 RECORD RETENTION 6.1'0.1 The following records shall be retained for at least five years:

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Records and logs of facility operation covering time interval a.

at each power level.

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Records and logs of principal maintenance activities, inspection, b.

repair and replacement of principla items of equipment related to nuclear safety.

I All REPORTABLE OCCURRENCE reports submitted to the COMMISSION.

c.

d.

Records of surviellance activities, inspections and calibrations

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required by these Technical Specifications.

Records of reactor tests and experiments.

e.

f.

Records of changes made to Operating Procedures.

g.

Records of radioactive shipments.

h.

Records of sealed source leak tests and results.

i.

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

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

Records-and drawing changes reflecting facility design modifi-a.

cations made to systems and equipment described in the Final Hazards Summary Report.

l b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

Records of facility radiation and contamination surveys.

c.

Records of radiation exposure for all individuals entering

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radiation control areas.

Records of gaseous and liquid radioactive material released to 7

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'the environs.

f.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

6-22 Amendment No. 45 YANKEE-ROWE I

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ADMINISTRATION CONTROLS g.

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

h.

Records of in-service inspections performed pursuant to these S

Technical Specifications.

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Records of Quality Assurance activities required by the QA

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Manual.

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Records of reviews performed fo: changes made to procedures or

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equipment or. reviews of tests and experiments pursuant to 10 R

M r.FR 50.59.

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Records of meetings of the PORC and the NSAR Committee.

l 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposures.

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a 6.12 RESPIRATORY PROTECTION PROGRAM

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ALLOWANCE 6.12.1 Pursuant to 10 CFR 20.103(c)(1)'and (3), allowance may be made 3

for the use of respiratory protective equipment in conjunction with i

activities-authorized 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 1 Column 1, of 10 CFR 20, subject to the following conditions and limitations:

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

exceeded.

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b.

If the radioactive material is of such form that intake

[F through the skin or other additional route. is likely, individual

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exposures to radioactive material shall be controlled so that

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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 i

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 1, Column I,. of 10 CFR 20.

V l-Amendment No. 45 YANKEE-ROWE 6-23 I

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For radioactive materials designated "Sub" in the " Isotope"-

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_ d=2 column of Appendix B, Table I, Column 1 of 10 CFR 20, the

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concentration " 'ne specified shall be based upon exposure to the material as an external radiation source.

Individual

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..j the limitation on individual dose in 520.101. These materials

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PROTECTION PROGRAM 6.12.2 In all operations in which adequate limitation of the inhalation

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of radioactive material by the use of process or other engineering controls is impracticable, the licensee may permit an individual in a

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restricted area to use respiratory-protective equipment to limit the

J inhalation of airborne radioactive material, provided

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The limits specified in 6.12.1 above,.are not exceeded.

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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 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 6.12-1 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 c

z evaluating the exposures.

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l Amendment No. 45 YANKEE-ROWE 6-24

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c.

The licensee advises each respirator user that he may leave ma; the area at any time for relief from respirator use in case of equipment malfunction, physical or psychological discomfort,

'=r or any other condition that might cause reduction in' the protection afforded the wearer.

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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-288.2-1969). Such a program shall include:

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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.

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3.

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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Written procedures for maintenance to assure full effec-tiveness of respiratory protective equipment, including issuance, cleaning and decontamination, inspection, repair,~and storage.

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.

6.

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

e.

The licensee uses equipment approved by the U.S. Bureau of Mines under its appropriate Approval Schedules as set forth in Table 6.12-1.

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 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 6.12-1.

i YANKEE-ROWE 6-25 Amendment No. 45 l

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Unless otherwise authorized by the Comission, the licensee

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shall not assign protection factors in excess of those specified m.;

in Table 6.12-1 in selecting and using respiratory protective Th equipment.

s REVOCATION WE.

ss-6.12.3 The specifications of Section 6.12 shall be revoked in their

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entirety upon adoption of the proposed change to 10 CFR 20, Section F si

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20.103, which would make such provisions unnecessary.

6.13 HIGH RADIATION AREA 6.13.1 Paragraph 20.203 " Caution signs, labels, signals, and contro1r " In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2),

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each high radiation area in which the intensity of radiation is 1000 mrem /hr 4=

t or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance f a Radiation Work Permit.* An individual or group of individuals permitted to enter n=

such areas shall be provided with one or more of the following:

g a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

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b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the -

area have been established and personnel have been made know-ledgeable of them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for proitding positive

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control over the activities within the area and who will perform radiation surveillance at the frequency specified in the RWP.

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The surveillance frequency will be established by the Plant Health Physicist.

The above procedure shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the key shall be maintained under the administrative control of the shift supervisor on duty and/or the Plant Health Physicist.

• Health Physics personnel shall be exempt from the RWP issuance requirement

==*e,g-"T during the performance of their assigned radiation protection duties, pro-G.

viding they are following plaat radiation protection procedures for entry into high radiation areas.

Amendment No. 45 YANKEE-ROWE 6-26 4

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TABLE 6.12-1 h

PROTECTION FACTORS FOR RESPIRATORS

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k PROTECTION FACTORS (Z)

GUIDES TO SELECTION OF EQUIPMENT

• 5 PARTICULATES AND BUREAU OF MINES / NATIONAL INSTITUTE-VAPORS AND GASES FOR OCCUPATIONAL SAFETY AND HEALTH DESCRIPTION.(7)

MODES (l).

EXCEPT TRITIUM APPROVALS (*or schedule superseding for OXIDE (3) equipment type listed.)

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AIR-PURIFYING RESPIRATORS Facepiece, hal f-maski),

HP 5

30 CFR Part 11 Subpart K Facepiece, full NP 100-30 CFR Part 11 Subpart K II. ATMOSPHERE-SUPPLYING.

RESPIRATOR 1.

Airline respirator Facepiece, hal f-mask CF 100 30 CFR Part 11 Subpart J g

g, Facepiece, full CF 1,000 30 CFR Part 11 Subpart J t

Facepiece, full D

100 30 CFR Part 11 Subpart J -

N Facepiece, full PD 1,000 30 CFR Part 11 Subpart J Hood CF (s) 30 CFR Part 11 Subpart K Suit CF (5)

(6) ii t

2.

Self-contained breathing 3

i g

apparatus (SCBA) g_

Facepiece, full D

100 30 CFR Part 11 Subpart H g

Facepiece, full PD 1,000 30 CFR Part 11 Subpart H Facepiece, full R

100 30 CFR Part 11 Subpart H s

p-5 1 III. COMBINATION RESPIRATOR Any combination of air-Protection factor for m

purifying and atmosphere-type and mode of opera-30 CFR Part 11 5 ll.63(b) supplying respirator tion as listed above Amendraent No. 40 June 16, 1977 wm* *

.+

+e

=-e'*

r

,e e e e,

I!5!

iq i ldJ 21' u.. i

~

9:

TABLE 6.12-1 (Continued)

=

TABLE NOTATION (1) See the following symbols:

h.b CF:

continuous flow D: demand NP:

negative pressure (i.e., negative phase during inhalation)

PD:

pressure demand (i.e., always positive pressure)

R:

recirculating (closedcircuit)

(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 a) plied to the ambient airborne u

concentration to estimate t1e concentration inhaled by the

=

wearer according to the following fonnula:

=

Concentration Inhaled Ambient Airborne Concentration

~

=

Protection Factor (b)

The protection factors apply:

(i) only for trained individe ils wearing properly fitted 1

respirators used and mair.ained under supervision in a well-planned respiratory protective program.

(ii) for air-purifying respirators only when high efficiency labove 99.9% removal efficiency by U.S. Bureau of Mines type dioctyl phthalate (DOP) testl particulate filters and/or sorbents appropriate to the hazard are used in ataospheres not deficient in oxygen.

(iii) for atmosphere-supplying respirators only when supplied with adequate respirable air.

(3)

Excluding radioactive contaminants that present an absorption or submersion hazard. For tritium oxide approximate'y half of the intake occurs by absorption through the skin so that an overall protection 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.

YANKEE-ROWE 6-28 Amendment No. 45 l

l I

a.

l

TABLE 6.12-1 (Continu~d)

TABLE NOTATION (4) Under' chin only. Not recommended for use where it might be possible for the ambient airborne concentration to reach instan-taneous values greater-than 50 times the pertinent values in Appendix B, Table I, Column 1 of 10 CFR Part 20.

(S) Appropriate protection factors must be determined taking account of the design of the suit or hood and its permeability to the contaminant under conditions of use.

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

(6)

No approval schedules current available for this equipment.

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

(7)

Only for shaven faces and where nothing interferes with the seal of tight fitting facepieces against the skin.

Hoods and suits are excepted.

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 useo to the extent that they do not exceed the protection factors 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 haz:rds. The selection and use of respirators for such c'ecumstances 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 CFR Part 20 are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations.

Under such circumstances, limitaticris on occupancy may have to be gov-erned by external dose limits.

YANKEE-ROWE 6-29 Amendment No. 45

.