ML19260A166

Tech Spec Change Request 58 Supporting Licensee Request to Change App a to License DPR-50 Re Establishment of Min Qualification Requirements for Radiation Protection Supervisors at Facility.Certificate of Svc Encl

ML19260A166
Person / Time
Site:	Three Mile Island
Issue date:	05/23/1977
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A165	List: ML19260A164 ML19260A166
References
NUDOCS 7910290774
Download: ML19260A166 (6)

Text

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IETROPOLITA'I EDISON CO!GA'iY JERSEY CENTRAL POWER & LIGHT COMPANY AND P M SYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chance Recuest No. 58 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License Iio. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON COMPANY By lice" President Sworn and subscribed to me this day of , 197T.

Notary Public e p ,,

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1. $ } .g 1480 271 7 910 290 //y

Three *'ile Island Unclear Station, Unit 1 (iAI-1)

Operating License Uo. DPR-50 Docket Ho. 50-289 Technical Snecification Chance Request No. 58 The licensee requests that the attached changed pagcc replace pages 6-20, 6-2]

cnd 6-22 of the existing Technical Specifications, Appendix A.

Reacons for Proposed Change The reacon for this revision is to @tablish the minimum qualification requirements for the TMI l Supervisor-Radiation Protection and Chemistry and the Radiation Protection S2pervisor.

Safety Analysis Justifying Change The proposed change is administrative in nature and does not involve an unreviewed safety question in that (i) the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previoucly evaluated in the safety analysis report is not increased; (ii) the possibility for an accident or malfunction of a different type than any evaluated previoucly in the cafety analysis report is not created; and (iii) the margin of safety defined in the basis for any technical specification is not reduced.

1480 272

g  %.:o r t .f tcsining and quitficaticn fm curent :Mebec of the plant taff.

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

1. Records of quality assurance activities. required by the CQA Plan.

J. Records of reviews performed for chm,ges made o procedures or equipment or reviews of tects and expc*inents pursuant to 10 CFR 50 59

k. Plant Operations Review Committee and General Office Review Board Minutes.

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

16.11.1 Supervisor-Radiation Protection & Chemistry The Radiation Protection and Chemistry Supervicor shall have a minimum of five years of power station or applicable industrial experience in design, construction, startup, operation, maintenance, or technical services, of which a minimum of one year shall be nuclear experience. He shall hold a minimum of a four-year degree in an engineering or scientific field.

16.11.2 Radiation Protection Supervisor The Radiation Protection Supervisor shall have a minimum of five years of experience in radiation protection at a nuclear facility at the foreman and/or supervisory level. He should have a minimum of 'vo years of related technical training. A maximum of three years of related technical or academic training chall apply towards the minimum five years of e:xperience.

6.12 REST !RATORY PROTECTION PROGRAM

'D Y \D QUWMh ALLOWAUCE g a 6.12.1 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 authorized by the operating license for this facility in determining whether individus1s in restricted areas are exposed to concentrations in excesc of the limite specified in Appendix B, Table 1, Column 1, of 10 CFR 20, subject to the following conditions and linitations:

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

b. If tne radiouctive raterial is of such form that intako through the skin er other additional ro'ne 13 likely, individuni exposures to radioac' V- aterial 3 hall be controllmi 30 that the radicactive conten: o ' any critical orrun frei all routes of intake averaged over - ca..meutive days doc. rc exc si that which would result from inb u _ c e. radicad ivo "!al fm 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> at the pertinent ccn s tr e. 3n values nro; k. . Arm dix 3, Table I, Colu r.1, of 10 Tr' 2'.

6-20 1480 273

c. For radioacti- materials designeted "Sub" in 'e " Isotope" coluen of Appendix b. fable I, Column 1 of 10 CFR 20, .he concentration value specified shall be based upon exposure to the naterial as ca external radiation source. Individual exposures to these materials shall be accounted for as part of the limitation on individusl done in 20.101. These materials shall te subjcet to applicable process and other engineerin6 controls.

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D990j 3D ~N "3 FFOTECTION FROGRA'I Jg @g]{ _

6.12.2 In all operations in which adequate limitation of the inhalation of radioactive material by the use of process or other engineering controls is impraecicable, the licensee may rermit 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 6.12.1 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 cpecified in Appendix E, 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 vorn =ay 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 evaluating the exposures.

c. 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.

d. The licensee naintains 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 (AUSI Z88.2-1969). 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.

h. Written procedures for maintenance to assure full effectiveness of reapirstory protective equipment, including iscurance, cleanicc snd cecontarination, inspection, repair, and storage.

6-21 1480 274

5 Uritten operationel 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 asacas protection actually provided.

e. The licensee shall use equipment approved by the U. S. Bureau of Mines (or the National Institute of Occupational Safety and Health, as applicable) under its appropriate Approval Schedules as set forth in Table 6.12-1. Equipment not approved under U. S. Bureau of Mines (or National Institute of Occupational Safety and Health, as applicable)

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 equipnent are at least equal to those afforded by U. S.

Bureau of Mines (or National Institute of Occupational Safety and Health, as applicable) approved equipment of the same type, as specified in Table 6.12-1.

f. Unless.otherwise authorised by the Conmission, the licensee shall not assign protection factors in excess of those specified in Table 6.12-1 in selecting and using respiratory protective equipment.

6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20:

a. Each High Radiation area (100 arem/h or greater) in which the intensity of radiation is 1000 crem/h or less shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit. Any individual or group of individuals permitted to enter such areas shall by provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. Each High Radiation Area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.13.1(a) above, and in addition locked doors shall be provided to prevent unauthorised entry into such areas and the keys shall be maintained under the administrative control of the Radiation Protection Supervicar/ Foreman or the Ghift 'orenan on duty.

f-?2 1480 275

U:IITED STATES OF AMERICA UUCLFAD. REGULATORY CCICIICSIOi I:! THE ?!ATTER OF DOCEzT no. 50-289 LICENSE NO. DPR-50

!!ETROPOLITA:I EDICON COMPANY Tuis is to certify that a copy of Technical Specification Change Request

!!o . 58 to Appendix A of the Operating License for Three Mile Island Huclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Ccnmission and baen served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows: .

i:r. Weldon B. Arehart Mr. Harry 3. Reese, Jr.

Ecard of Supervisors of Board of County Co==issioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Herrisburg, Pennsylvania 17120 METROPOLITAI EDISON COMPAIIY

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By _ A Vfce Presidhnt Otted: May 23, 1977 1480 276