ML19210B422

Tech Spec Request 57 to DPR-50,App A,Re Respiratory Protection Programs.Certificate of Svc Encl

ML19210B422
Person / Time
Site:	Three Mile Island
Issue date:	11/15/1977
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19210B421	List: ML19210B420 ML19210B422
References
NUDOCS 7911080636
Download: ML19210B422 (5)

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. UNITED STATES OF AMERICA NUCLEAR REGULATORY C0!C4ISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 MEIROPOLITAN EDISON COMPA'IY This is to certify that a copy of Technical Specificaticn Change Request No. 57 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regtlatory Cc=ission and been served on the chief executives of Londent'.erry Township, Dauphin County, 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 Comissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Read Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON CCMPANY

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/ Vice President Dated: November 15.1977 4

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METROPOLITri EDISO:I CCleA'iY JERSEY CZ:ITRAL PC'4ER & LIGHT C0!GETf AND PENNSYLVA' IIA ELECTRIC CClerIY TEREE MILE ISLA'ID I;UCLEAR STATION UNIT 1 Cperating License Iio. DFR-50 Docket No. SC-2e9 Technical Stecification Chance Recuest No. 57 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. 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:s EDISO:I CC!GMrf By h Vice' President

-E a Sworn and subscribed to me this O day of ', 1977.

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-/-e -mw Notary Public NOT/ V FC L:C Raatu g Ec=: 1.m 7a h*) M C$s:Cf!Es ftS.'4CV.13.'373 1584 004

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.' 'y Three > Ele Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50

. Docket No. 50-289 Technical Snecification Chance Recuest No. 57 The licensee requests that the attached changed pages replace pages c-20 25 of the existing Technical Srecifications. The licensee also requests that this change, should it te approved by the Cenmission, become effective on Decester 29, 1977 Reascns for Change Recuest 10 CFP 20.103 (f) requires that respiratory protecticn programs shall neet the require =ents of Reg. Guide 8.15, by December 29, 1977 Therefore, the details of our respiratory protection progra= contained in the Technical Specification are to be replaced with a state =ent ec=ritting us to Reg. Guide 8.15 as of December 29, 1977 Safety Analysis Justifying Change Rec _uest

1. Cc==itting to Eeg. Guide 8.15 assures that the respiratory pro-tection program is at least equivalent to that as outlined in the Technical Specifications. Therefore, neither the probability of cecurrence nor the consequences of an accident or =alfuction of equipment important to safety and previcusly evaluated in the safety analysis report is increased.

2. The possibility for an accident or =alfuction of a different type than any evaluated previously in the safety analysis report is not created by the proposal. The change creates no potential for an accident 'thich was not studied in the FSAR.

3. The margin of safety as defined in the basis for any technical specification is not reduced by this proposal in that, no other section of the Technical Specifications is affected by this change.

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g. Records c  ; raining and qualification for trent menbers of

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the plant staff. ,

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

. i. Records of quality assurance activities required by the OQA Plan.

J. Records of re< '

performed for changes =ade to procedures or equip =ent or n:,us of tests and experiments pursuant to 10 CFR 50 59

k. Plant Operaticas Review Con =ittee and General Office Review Board Minutes.

6.11 RADIATION PFCTICTIC5 PROGPEI 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 persennel radiation exposure.

6.11.1 Supervisor-Radiatics Protectica & Chemistry The Superviscr-Radiation Protection and Chemistry shall have a bachelor's degree or equivalent in an engineering or scientific subject. The folleving are equivalent to the bachelor's degree: (a) h years of .

fer=al schecling in science er 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 ec=bination of the above totaling h years. In addition to the above requirements, he should have a * '--- cf five years of power station or applicable industrial experience in design, construction, startup, operations, =aintenance, or technical services, of which a =inimum of one year shall be nuclear experience.

6.11.2 Radiatien Protection Supervisor 58-A The Radiation Protection Supervisor shall have a =ini=u= 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.

Bases The ec=bined qualifications of the Superviscr-Radiation Protection and Chemistry and the Radiation Protection Supervisor are equivalent to those require =ents stated in Reg. Guide 1.8 for the Radiation Protection Manager.

6.12 RESPIRATORY PROTECTION PROGRAM The Respiratory Protection Program shall meet the requirement of Reg.

Guide 8.15, October 1976, " Acceptable Progra= for Respiratory Protection".

Page 6-21 deleted.

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6.12 HIGH hADIATION AREA 6.12.1 In lieu of the " control device" or " alar = signal" required by paragraph 20.203(c)(2) of 10 CFR 20:

a. Each High Radiation area (100 =re /h or greater) in which the intensity of radiation is 1000 nrem/h er less shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring issuance of a Radiation

'Jork Per=it. Any individual or group of individuals permitted to enter such areas shal3 be provided with a radiation .=cnitoring device which cen*.inuously indicates the radiation dose 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 addition locked doors shall be provided to preven unauthorized entry into such areas and the keys shall be =sintained under the administrative c:ntrol of the Radiation Protection Supervisor /?creman or the Shift Foreman en duty.

Pages 6-23 to 6-25 deleted.

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