ML20133M395

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Amend 25 to License DPR-73,changing Section 2.1.2 Re Gaseous Effluents of App B Tech Specs.Epithet Used to Describe Testing of Radiation Vent Monitors Changed to Instrument Functional Test to Achieve Consistency in Tech Specs
ML20133M395
Person / Time
Site: Crane 
Issue date: 10/21/1985
From: Snyder B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133M397 List:
References
NUDOCS 8510250591
Download: ML20133M395 (4)


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GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION DOCKET NO. 50-320 THREE li!LE ISLAND NUCLEAR STATION UNIT NO. 2 i

AMENDMENT TO FACILITY OPERATING LICENSE l

1 Amendment No. 25 i

License No. DPR-73 1.

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

A.

The application for amendment by GPU Nuclear Corporation (the licensee),datedApril 12, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.

The facility will be operated in conformity with the License, the Order for Modification of License dated July 20, 1979, the appli-l cation for amendment, the provisions of the Act, and the rules and regulations of the Comission;

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C.

There is reasonable assurance (i) that the activities authorized by L

this amendment will 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; I

D.

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

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

i 2.

Accordingly, the license is amended by changes to the Operating l

License Technical Specifications as indicated in the attachment to this license amendment and by changing paragraph 2.C (2) to Facility t

l Operating License No. DPR-73 to read as follows:

l 2.C (2)TechnicalSpecifications The Technical Specifications contained in Appendices A and D, as revised through Amendment No. 25 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and all Comis-i sion Orders issued subsequent to March 28, 1979, r

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This license amendment is effective as of the date of its? issuance.

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FOR THE NUCLEAR REGULATORY COMfilSSION 3

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1 Bernard J. Snyder, Program Director 4

Three Mile Island Program Office Office of Nuclear Reactor Regulation Date of Issuance:

October 21, 1985 l

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FACILITY OPERATING LICENSE NO. DPR-73 i

j DOCKET NO. 50-320 i

4 The following pages of the Appendix "B" Technical Specifications to the Facility Operating License has been modified as a result of this Safety

.I' Evaluation. Therefore, you should replace your present page with that

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enclosed.

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2-10 i

LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Specification (Cont'd) i j

F.

During power operation, the con-i densor vacuum pump discharge shall be continuously monitored for gross i

i gaseous activity.

The monitor shall not be inoperable for more than a l

l week. Whenever this monitor is l

inoperable, a grab sample shall be

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taken daily and analyzed for i

gross radioactivity.

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G.

Facility records shall be main-tained of radioactive concentration, j

release ratio and volume of each batch of gaseous effluents released I

and the length of time over which j

release occurred.

Estimates of the j

error associated with each reported value should be included in facility 1

j records.

H.

At least annually, automatic i

initiation and closure of the Waste l

Gas Decay Tank Discharge valve on i

alarm of (Unit 2: WDG-R-1480) shall 1

be verified.

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l I.

The Unit Vent monitors for TMI-2 i

(HP-R-219, sip-R-219A,HP-R-225, j

HP-R-226), respectively, shall be calibrated at least every eighteen months by means of a known i

radioactive source.

These detectors j

shall have an instrument functional l,

test at least monthly, and a sensor i

check at least daily, to verify that the read-out device is indicated as expected, i

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The specified levels provide Specification A. through I., above, reasonable assurance that the require that suitable equipment to resulting annual exposure rate from monitor the radioactive gaseous

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noble gases at any locatior it the releases are operating during any i

site boundary will not exceed 10 period these releases are taking millf rems per year.

At the same place.

AMEN 0 MENT 25 i

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