ML19291B587
| ML19291B587 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/06/1977 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19291B586 | List: |
| References | |
| NUDOCS 7911080622 | |
| Download: ML19291B587 (6) | |
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- CI'ROPOLITA'I EDISO:I COMPA IY JERSEY CENTRAL PO'a*ER & LIGHT COMP %iY A'ID PE'INSYLVANIA ELECTRIC CCMPA:IY THREE MILE ISLA:iD NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Snecification Change Recuest No. 58, Am. A This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License :Io. 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.
METROPOLITA:I EDISO:7 COMPA:IY Ry /, h Vice President t
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M Sworn and subscribed to me this U
day of
, 1977.
iotary Public #
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NelfM 3d a s Qu.7 y, E 1 My Ocmmiss:cn Egres,h 13, ;j;;
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UNITED STATES OF AMERICA NUCLEAR REGULATORY CCMMISSION IN ':"/.E Mkilu CF DOCKET NO. 50-289 LICENSE NO. DPR-50 METRCPOLITAIT EDISON COMPANY This is to certify that a ecpy of Technical Specificatien Change Request No. 58, Amendment A to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given belcv, been filed with the U. S. Nuclear Regulatory Ccmmission and been served en the chief executives of Londonderry Township, Dauphin Ccunty, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.
Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METP,0POLITAN EDISCN COMPA'IY s
/
/
B-Vice President Dated:
October 6, 1977 1583 346
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Cperating License No. DPR-50 Decket No. 50-289 Technical Stecification Change Recuest No. 58, Amendment A The licensee requests that the attached changed pages replace pages 6-20, 6-21 and 6-22 of the existing Technical Specifications, Appendix A.
Reasons for Fronosed Change The reason for this revision is to establish the minimum qualification requirements for the TMI-l Supervisor-Eadiation Protection and Chemistry and the Radiation Protection Supervisor.
Safety Analysis Justifyinz Chance 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 calfunction of equipment important to safety previcusly evaluated in the safety analysis report is not increased; (ii) the possibility for an accident or =alfunction of a different type than any evaluated previously in the safety analysis report is not created; and (iii) the margin of safety defined in the basis for any technical specification is not reduced.
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Records of tral...ng and qualification for currer. members of the g.
plant staff.
Records of in-service inspections performed pursuant to these Technical h.
Specifications.
1.
Records of quality assurance activities required by the OQA Plan.
J.
Records of reviews performed for changes =ade to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50 59 k.
Plant Operations Reviev Committee and General Office Review Board Minut es.
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, =aintained and adhered to for all cperations involving personnel radiation exposure.
6.11.1 Supervisor-Radiation Protection & Chemistry The Supervisor-Radiaticn Protection and Chemistry shall he.ve a bachelor's degree or equivalent in an engineering or scientific subject. The folleving are equivalent to the bachelor's degree:
(a) 4 years of for=al schooling in science or engineering (b) h years of applied radiation protection experience at a nuclear facility (c) h years of operational or technical experience / training in nuclear power (d) any combination of the above totaling h years.
In addition to the above requirements, he should have a minimum of five years of power station or applicable industrial experience in design, constructicn, startup, operations, maintenance, or technical services, of which a minimum of one year shall be nuclear experience.
6.11.2 Radiation Protection Supervisor Tne Radiation Protection Supervisor shall have a minimum of five years of experience in applied radiation protection at a nuclear facility at the foreman and/or supervisory level.
In addition he should have a minimum of two years of related technical training.
v,,.n The ccabined qualifications of the Supervisor-Radiation Protection and Chemistry and the Radiatien Protect!cn Supervisor are equivalent to those requirements stated in Reg. Guide 1.8 f;r the Radiation Protection Manager.
6.12 RESPIRATCRY PROTECTION PROGRAM ALLOWANCE 6.12.1 Pursuant to 10 CFR 20.103(c)(1) and (3), allevance may be mcde for the use of respiratory protective equipment in conjuncticn with activities authorized by the operating license for this facility in determining whether individuals in restricted areas are expcsed to concentratiens in excess of the limits specified in Appendix 3, Table I, Colu=n 1, of 10 CFR 20, subject to the folleving conditions and limitations:
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a.
The li=its pros ed in Secticn 20.103(a) and (c.
aall not be exceeded.
b.
If the radicactive caterial is of such form that intake through the skin or other additional route is likely, individual exposures to radicactive =sterial shall be controlled so that the radioactive content of any critical organ frc= all routes of intake averaged over ? consecutive days does not exceed that which would result frc=
inht'.ing such radicactive material for h0 hours at the pertinent concentration values provided in Appendix 3, Table I, Colu=n 1, of 10 CFR 20.
For radicactive materials designated "Sub" in the " Isotope" column c.
of Appendix B, Table I, Colu=n 1 of 10 CFR 20, the cencentrati-value specified shall be based upon exposure to the material as an external radiaticn source.
Individual exposures to these materials shall te accounted for as part of the limitation en individual dose in 20.101.
These materials shall be subject to applicable process and other engineering centrols.
PROTECTION PROGRAM 6.12.2 In all operaticns in which adequate limitation of the inhalaticn of radicactive material by the use of process or other engineering centrols is impracticable, the licensee may pennit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne radioactive materisl, pro tided:
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 specified in Appendix B, Table I, Column 1, of 10 CFR 20.
For the purpcses 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 vorn.
If the intake of radioactivity is later determined by cther 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 frc= respirator use in case of equipment
=alfunction, physical or psychological disec= fort, or a37 cther condition that might cause reduction in the protection afforded the vearer.
d.
The licensee maintains a respiratory protective program adequate to assure that the requirements above are met and incorpcrates practices fcr respiratory protection consistent with these recc== ended by the American National Standards Institute (ANSI Z88.2-1969). Such a program shall include:
1.
Air sampling and cther surveys sufficient to identify the hacard, to evaluate individual expcsures, and to permit proper selecticn of respiratory protective equipment.
2.
'4ritten procedures to assure proper selection, supervision, and training of personnel using such protective equipment.
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a 3.
Written procedures to assure the adequate fitting of re pirators; and the tecting of respiratcry protective equip =ent for operability immediately prior to use.
h.
Written procedures for =aintenance to assura full effectiveness of respiratory prctective equipment, including issuance, cleaning and decontaminatien, inspection, repair, and storage.
5.
Written operatienal and a ninistrative precedures for proper use of respiratory protective equipment including provisions for planned limitations on working ti=es as necessitated by operational conditions.
6.
Bioassays and/or whole bcdy counts of individuals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection actually provided.
~
e.
The licensee shall use equipnent approved by the U. S. Bureau of Mines (or the National Institute of Occupational Safety and He,alth, as applicable) under its appropriate Approval Schedules as set forth in Table 6.12-1.
Equipment cet 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 de=cnstrate by testing, er en +.he basis of reliable test information, that the material ar.d perfor=ance characteristics of the equipment are at least equal to those afforded by U. S.
Bureau of Mines (or National Institute of Cccupational Safety and Health, as applicable) appreved equipment of the same type, as specified in Table 6.12-1.
f.
Unless otherwise authorized by the Com=ission, the licensee shall not assign protection factors in excess of tnose specified in Table 6.12-1 in selecting and usir.g respiratory protective equipment.
6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alar = signal" required 'cy paragraph 20.203(c)(2) of 10 CFR 20:
Each High Radiaticn area (100 =re=/h or r;reater) in which the intensity a.
of radiation is 1000 =re=/h or less shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring is suance of a Radiation Work Permit. Any individual or group of individuals pernitted to enter such areas shall by provided with a radiation =cnitoring device which continuously indicates the radiation dc.se rate in the area.
b.
Each High Radiation Area in which the intensity of radiation is greater than 1000 =re=/hr shall be subject to the provisions of 6.13.1(a) above, and in edditicn locked doors shall be provided to prevent unautberized entry into suen areas and the keys shall be
=aintained under the aininistrative control of the Radiation Protec..cn Superviscr/ Fore =an er the Shift Fc' reman en duty.
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