ML19220C152
| ML19220C152 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/05/1978 |
| From: | Moore V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19220C149 | List: |
| References | |
| TM-0167, TM-167, NUDOCS 7904280298 | |
| Download: ML19220C152 (4) | |
Text
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METRCf0LITAN EDISON C0f9ANY JERSEY CENTRAL POWER AND 1.IGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCXET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMEND 4ENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. DPR-73 1.
The Nuclear Regulatory Connission (the Comission) has found that:
A. ~ The application for amendment by Metropolitan Edison Coc:pany, Jersey Central Power and Light Company, and Pennsylvania Electric Cernpany (the licensees) dated April 25,1978 and May 19, 1978, cecplies with the standards and requirements of the Attraic Energy Act of 1954, as amended (the Act) and the Cocmission's rules and regulations set forth in 10 CFR Chaptar I; 8.
The facility will operate in confamity with the application, the provisions of the Act, and the rules end regulations of the Conmission; C.
There is reasonable assuranen (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) t that such activities will be conducted in compliance Mth the Cccmission's regulations; The issuance of this amendment will not be inimickl to the D.
comon defense and security or to the health and safety of the public; and
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2 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
F.
Publication of notice of this amendment is nct required since it does not involve a significant hazards consideration nor amentent of a license of the type described in 10 CFR Section 2.105(a)(2).
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicatHi in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. CPR-73 is hereby amended to read as folicws:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendent No. 7, are hereby incorporated in the license. Hatropolitan Edison Caspany shall operate the facility in accordance with the Technical Specifications.
3.
Paragraph 2.E.(2) of the license is hereby deleted in its entirety.
4.
This license anendnent is effective as of the date of its issuance.
F02 TliE NUCLEAR REGJLATORY C0fEISSICM 4
Yoss A. Moore, Assistant Directer for Environmental Projects Division of Site Safety and Environmental Analysis Attachsent:
Change to tha Technical Specifications Date of Issuance:
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AMAC2C?,7 TO LICZ'.!SE A'E'!D'E'!T AME'iDMTNT TO. 7 TO FACILI'!? CPEFATING LICZ'!SE !!O. DPR-73 DOCKZT !!O.30-320 Revise Appendix 3 Technical Specifications as follcws:
Remove page 2-3 and insert the attached revised page 2-3.
The changed area on the revised page is shcun by a =arginal line.
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2-3 LIMITING CONDITICN's FCR CPERATION 2.C MONITCRING REQUIPEMENTS Soecificatien (Cent'd)
See:ification (Cont'd) causes and describing the proposed D.
Facility records shall be maintaine'd progra:n of action to reduce such of the radicactive c:ncentratiens and release rates.
volume before dilutten of each baten of liquid effluent released, and the average dilution flow and length of tire over which each discharge cccurrec.
Estimates of the error associated with each recorted value should be included in facility records.
E.
Radioactive licuid waste sanpling and activity analysis shall be "For the purposes of this specification, perfomes in accordance with the MPCw(163 hour0.00189 days <br />0.0453 hours <br />2.695106e-4 weeks <br />6.20215e-5 months <br />) for Xe-133 is 5 x 10-3u Table 2.3-1.
Pricr to the release C1/ml. The MPCy (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) for Xe-135 is of each batch of licuid efflent, a 1 x 10-32 C1/mi.
sample shall be taken from that batch and analyzed for the concentration of each significant gamma emitter to demonstrate compi f ance with Speci fica-tion "a" using the ficw into which the effluent is discharged.
F.
The licuid effluent radiation monitors RM-L5 and WCL-R-1311 shall be calibrated at least cuarterly by means of a kncwn radioactive source.
RM-L6 and WCL-R-1311 shall also have an instrument channel test monthly and a source check prior to each discharge to verify that the read-cut device is indicatino as expected.
G.
The ability of WDL-V-257 and WCL-V-99 to close autcoatically on receipt of a high radiation alar,
signal from Fit-L5 and WCL-R-1311 shall be checked annually.
Bases Bases Liquid radioactive waste release Specifications A, S, and C, above levels to unrestricted areas should recuire that suitable ecuipncat to be kept "as low as practicable
- and monitor the release of radioactive are not to exceed the concentration materials in licuid effluents are
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limits specified in 10 CFR 20.
Tne operating during any period these objective provides reasonable as-releases are taking place.
surance that the resulting annual exposure to an individual in of f The surveillance recuireeents given site areas will not exceed 5 milli-in the re-aining specifications cro-rem per year. This assurance is vide assurance that licuid wastes are based on the fact that the Succue-properly controlled nd menitored hanna River will dilute the licuid during any planned release of radin-effluents upon their release fren active materials in i f cuid ef fluents OO h1 00 UJU
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