ML20127K463

Forwards Change 1 to DPR-22 Assigning Protection Factors to Respiratory Equipment,Per 710315 Request to Change TS

ML20127K463
Person / Time
Site:	Monticello
Issue date:	04/28/1971
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Dienhart A NORTHERN STATES POWER CO.
References
NUDOCS 9211200410
Download: ML20127K463 (12)

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Docket No. 50-263 gg h Northern States Power Company ATTN: Mr. Arthur V. Dienhart

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Manager of Engineering ,

414 Nicollet Mall Minneapolis, Minnesota 55401 Change No. 1 Gentlemen: License No. DPR-22 Your letter dated iarch 15, 1971, requested authority to assign protection factors to the use of respiratory equipment and to make them part of the rechnical Specifications of Provisional Operating Licence :To. JPR-22 for the Monticello Nuclear Generating Plant E-5979.

wring our review of the proposad change, we informed your staff that certain modifications were ne< c.ssary to neet our regulatory requirements.

On the basis of our review of your proposed change, as modified, we have con-cluded that the change does not present significant hazards considerations not described or implicit in the Monticello Safety Analysis Report and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the "onticello Nuclear Generating Plant E-5979 in the proposed manner.

Accord ingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical specifications of Provisional Operating License ;;o. DPR-22 are hereoy changed as set forth in Attachment A to this letter.

Sincerely, Peter A. Morris, Director Division of Reactor Licensing

Enclosure:

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t License No.~DPR-22 Your letter dated March 15, 1971, requested authority to assign protec-tion f actors to the use of respiratory equipment and to make them part of the Technical Specifications of Provisional Operating License No. DPR-22 for the Monticello Nuclear Generaticg Plant E-5979. *

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During our review of the proy,o sed change, we informed your staff that certain

" modifications were necessary to meeb our regulatory' requirements and to make' your facility Technical Specifications, consistent with specifications approved for other facilities. Yodr/ staff indicated\- that these modifications were acceptable. '

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I On the basis of our review of your proposed change, na modified, we have con-cluded that the change does not present signif(cant hazards considerations l i

not described or implicit in the Monticello Saf 6ty Analysis 'Repo'rt and that " l there.is reasonabid assurance that the health,andN afety of the public" vill -

I not be' endangered'by operation of the Monticello Nu' ear Generating Plant ." "

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- . s Accordingly, pursuant to Section 50.59 of 10 CFR Part 50 Athe Technical

" Specifications changed andet of Provisional forth in Attachment , OperatingALicense to thisNo. letter.

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April 28, 1971 Docket No. 50-263 Northern States Power Company ATTN: Mr. Arthur V. Dienhart Manager of Engineering 414 Nicollet Mall Minneapolis, Minnesota 55401

- Change No. 1 Gentlemen: License No. DPR-22 Your letter dated March 15, 1971, requested authority to assign protection factors to the use of respiratory equipment and to make them part of the Technical Specifications of Provisional Operating License No. DPR-22 for the Monticello Nuclear Generating Plant E-5979.

During our review of the proposed change, we informed your staff that certain modifications were necessary to meet our regulatory requirements.

On the basis of our review of your proposed change, as modified, we have con-cluded that the change does not present significant hazards considerations not described or implicit in the Monticello Safety Analysis Report and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the Monticello Nuclear Generating Plant E-5979 in the proposed manner.

Ac c o rd ing ly , pursuant to Section 50.59 of 10 CFR Part 50, :he Technical Specifications of Provisional Operating License No. DPR-22 are hereby

! changed as set forth in Attachment A to this letter.

Sincerely,

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Peter A. Morris, Director Division of Reactor Licensing

Enclosure:

Attachment A - Change to Technical Specifications

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L ATTACRMENT A Change No. I to Technical Specifications Provisional Operating License No. DPR-22

' Northern States Power Company Docket No. 50-263

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Change Specifications 6.2B in its entirety to read:

"6.2 B 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 protection program shall be organized, with the following

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exceptions, to meet the requirements of 10 CFR 20."-

a. Paragraph 20.203 " Caution signs, labels, signals and controls."

In lieu of the " control. device" or alarm . signal required by

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paragraph 20.203(c) (2); each high radiation area in which the

- intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance i

of a Radiation Work Permit and any individual or_ group of i

individuals permitted to enter such areas shall be provided with-a radiation monitoring device which continuously indicates the

, radiation dose rate in the area.

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

! -except that locked doors shall be provided to prevent unauthorized entry into these areas and the keys to these locked doors shall be i maintained under the administrative control of the- Shif t Foreman on duty.

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b. Pursuant to 10 CFR,20.103(c)(1) and (3), allowance may-be made

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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 area are.

l exposed to concentrations in excess of the limits specified in

'. Appendix B, Table _ I, Column .1, of 10 CFR 20, subject to the i- following conditions and limitations:

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c. Notwithstanding any exposure limit provided herein, the licensee shall, as a precautionary procedure, use process or other engineering t controls, to the extent practicable, to limit concentrations of radioactive materials in air to levels below those which delimit.

an airborne radioactivity area as defined -in 6 20.203(d)(1).

d. When it is impracticable to apply process or other engineering controls to limit concentrations of radioactive materials to levels below those which delimit an airborne radioactivity _ area as defined in 8 20.203(d)(1), and respiratory protective equipment is used to limit the inhalation of airborne radioactive material,

' the licensee may make allowance for such use in estimating exposures of individuals to such materials provided:

1. Intake of radioactive material by any individual within any period of seven consecutive days will not exceed that which would I result from inhalation 1/2/;3/ of such material 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week, at uniform concentrations specified in Appendix B, Table I, i Column 1 of 10 CFR Part 20.

2. 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 per-tinent values specified in Appendix B, Table I, Column 1 of this part. For the purposes of this subparagraph the concentration i

of radioactive material that is inhaled when respirators are worn t

i 1/ Since the concentration specified for tritium oxide vapor assumes equal intakes by skin absorption and inhalation, the total intake i

permitted is twice that which would- result from inhalation alone at the concentration specified for H3 S in Appendix B, Table I, Column 1 for _

40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.

2/ For radioactive materials designated "Sub" in the " Isotope" column

of the tabic, the concentration value specified is based upon exposure to the material as an external radiation source. Individual exposures l to these materials shall be accounted for as part of the limitation on l individual dose in 8 20.101. These_ materials-shall be subject to applicable precautionary procedures-of paragraph c, above.

_3/ For modes of intake other than inhalation,.such intakes must be con-l trolled, evaluated, and accounted for by techniques and procedures as may be appropriate to the circumstances of the e urrence- with proper con-sideration of critical organs andzlimiting os.

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may be initially estimated by dividing the ambient airborne con-centration by the protection factor specified in Table I attached I hereto for the respiratory protective equipment worn. If the intake of radioactivity is later determined by other measurements to have been' greater than that initially estimated, the greater quantity shall be used in evaluating exposures; if it is less than that initially estimated, the lesser quantity may be used in evaluating exposures.

3. The licensee advises each respirator user that he may leave the area at-any time for relief from respirator use in case of equip-ment malfunction, physical or psychological discomfort, or any-l othei condition that might cause. reduction in the protection j afforded the wearer.

4. The licensee maintains a respiratory protective program adequate-to assure that.the requirements of paragraphs 1 and 2., above, ane met.

Such a program shall include:

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

(b) Written procedures to assure proper seleccion, supervision, and training of personnel using such protective equipment, t

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

(d) Written' procedures for maintenance to assure full effective-ness of respiratory protective equipment, including issuance, l

cleaning and decontamination,-inspection, repair, and-storage. <

l (e) 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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(f) Bioassays and/or whole body counts of individuals, and

, other surveys, as appropriate, to evaluate individual exposures and to assess protection actually provided.

(g) Records sufficient to permit periodic evaluation of the adequacy of the respiratory protective program.

5. The licensee uses equipment approved by the U. S. Bureau of

Mines under its appropriate Approval Schedules as set forth in Table I below. Equipment not approved under U. S. Bureau of Mines Approval Schcdules may 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 I below.

6. Unless otherwise authorized by the Commission, the licensee does not assign protection factors in excess of those specified in Table I below in selecting and using respiratory protective equipment.

7. These specifications with respect to the provisions of 5 20.103 shall be superseded by adoption of proposed changes to 10 CFR 20, Section 20.103, which would make this specification unnecessary.

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TABLE I TO SPECIFICATION 6.2 B PROTECTION FACTORS FOR RESPIRATORS PROTECTION FACTORS 2/ GUIDES TO SELECTION OF EQUIPMENT PARTICULATES BUREAU OF MINES APPROVAL SCHEDULES

• DESCRIPTION MODES N AND VAPORS AND FOR EQUIPMENT CAPABLE OF PROVIDING AT GASES EXCEPT LEAST EQUIVALENT PROTECTION FACTORS 3

TRITIUM OXIDE ] *or schedule superseding for equipment of type listed I. AIR-PURIFYING RESPIRATORS Facepiece, half-mask 4/ 7/ NP 5 21B3030CFRCFR 5 14.4(b)((4)

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Facepiece, full 7/ NP 100 21B S 14.4(b) 5); 14F 30 CFR 13 II. ATMOSPHERE-SUPPLYING RESPIRATOR

1. Airline respirator Facepiece, half-mask CF 100 19B 30 CFR S 12.2 I; TypeC(i)

Facepiece, full CF 1,000 19B 30 CFR S 12.2 ( Type C(i)

Facepiece, full 7_/ D 500 19B 30 CFR S 12.2 q Type C(ii)

Facepiece, full PD 1,000 198 30 CFR 912.2 1, Type C(iii)

Hood CF 5/ 6 Suit CF 5/

2. Sel f-contained breathing Hiiparatus(SCBA)

Facepiece, full 7/ D 500 13E 30 CFR 511.4 I; (1)

Facepiece, full ~ PD 1,000 13E 30 CFR S 11.4 ( (ii)

Facepiece, full R 1,000 13E 30 CFR 5 11.4 I, III. COMBINATION RESPIRATOR Any combination of air- Protection factor 19B CFR 512.2(e) or applicable purifying and atmosphere- for type and mode schedules as listed above supplying respirator of operation as listed above 1/, 2/, 3/, 4/, 5/, 6/, 7/, [These notes are on the following pages]

f M See the following symbols:

CF: continuous flow D: demand NP: negative pressure (i.e., negative phase during inhalation)

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

PP: positive pressure R: recirculating (closedcircuit)

U (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 airborne concentration to estimate the concentretion inhaled by the wearer according to the following fonnula:

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

(1) only for trained individuals wearing properly fitted respirators 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 V. S. Bureau of Mines type dioctyl phthalate (DOP) test) particulate filters and/or sorbents appronriate to the hazard are used ir. atmospheres not deficient in oxygen,

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

E Excluding radioactive contaminants that present an absorption or submersion 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 when atmosphere-supplying respirators are used to protect against tritium oxide. Air-purifying respirators are not reconenended for use against tritium oxide. See also footnote 5f, below, concerning supplied-air suits and hoods. l 7-e d

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5/ Appropriate protection factors must be determined taking account l

' of the design of the suit or hood and No its permeability to the protection factor greater i contaminant than 1,000 under conditions of use,shall be used except as authorize h

N No approval schedules currently available for this equioment.

Equipment must be evaluated by testing or on basis of available j ._

test information.

2/ Only for clean-shaven faces.

1 NOTE 1:

Protection factors for nespirators, as may be approved c

l by the U. S. Bureau of Mines according to approval sch

( 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 respiratoryThe selection and hazards exist in addition to radioactive hazards.

use of respirators for such circumstances should take into account approvals of the U. L. Bureau of Mines in accordance with its applicable schedules.

l NOTE 2: Radioactive contaminants for which the concentration values in Appendix B Table I nf this part are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under such circumstances, limi-tations on occupancy may have to be governed by external dose limits. ,

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