ML19290A499
| ML19290A499 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/10/1974 |
| From: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19290A447 | List: |
| References | |
| NUDOCS 7911070727 | |
| Download: ML19290A499 (3) | |
Text
m Mg UNITED STATES g, _4L -'Q/9 ATOMIC ENERGY COMMISSION
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WASW NGTON, D.C.
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%Qi METROPOLIT/m EDISCil CC"PA*1Y JERSEY CEliTRAL POWER A D LIGhi CCMPAflY PElit:SYLVA:ilA ELECTRIC CC;*PAliY DOCKET ti0. 50-239 (Three Mile Island tiuclear Station, Unit 1)
AMEf1DMEilT TO FACILITY OPERATIriG LICEllSE Amendment tio. 1 License fio. DPR-50 1.
The Atomic Energy Cocmission (the Comission) having found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (the licensees') dated May 6, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the cor. mon defense and security or to the health and safety of the public; and E.
Prior public notice of this amendment is not required since the amendment does not involve a significant hazards consideration.
2.
Accordingly, Paragraph 2.C.(2) of Facility License fo. DPR-50 is hereby amended to read as follows:
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"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, attached to Facility Operating License fio. DPR-50 are revised as indicated in the attachment to this license amendment. The Technical Specifications, as revised, are hereby incorporated in the license.
The licensees' shall operate the facility in accordance with the Technical Specifications, as revised."
3.
This license amendment is effective as of the date of its issuance.
FOR THE ATOMIC ENERGY COMMISSION Crida:1 si;n:d by
- !:ta A. !1sars Voss A. Moore, Assistant. Director for Light Water Reactors, Group 2 Directorate of Licensing
Attachment:
Change f!o.1 to Appendix A Technical Specifications License No. CPR-50 Date of Issuance: lAAY 101974 1557 518
Atend ent l'o.
1 Change !!o. 1 cn en ch
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- s Applicabi2ity Applies to the cperating statuc of the turbine cycle when fuel is in the core and the cupability of the decay removal cysten is exceeded.
Ob jecti ve To speciP/ =inint: conditions of the turbine cycle steam relieving capacity and etercency feedvater pumps to ensure capability to rezove decay heat equivalent to five percent of full pcuer.
Speci fi cation The reactor ecolant syste= shall not be heated above 2500F unless the folleving conditiene are cet:
3.h.1 Eighteen main steam cafety valves shall be operable.
3.h.2 Four of the six turbine by-pass valves are operable.
3.4.3 The turbine driven emergency feedvater purp and two half-sized notor-driven energency feedvater purps shall be cperabic.
3.h.h A minimum of 150,000 gallons of condensate available in the condensate stnrnge tanks.
3.h.5 System pipinc and valves, directly asccciated with the above cczpcnents operable.
3.h.6 Any ec ponent in 3.4.3 or 3.L.5 abcve rey be recoved frc: s ervi ce for purposes of taintenance for a period not to exceed LS hours.
If this pericd is exceeded the anit vill be placed in the cold shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
3.4.7 One of the half-sized motor-driven emergency feedvater pumps required by 3.4.3 cay be removed fron service for naintenance indefinitely provided that the reactor has never been operated
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at greater than 5% of rated thermal power.
Eases A reactor shutdcwn frca power requires renoval of core dec2y heat.
- ?ormal decay heat removal is by the stets generator with the cteam durp to the condenser when system te Perature is above 250 ? and by the decay heat renoval syste= below 250 F.
Therefore, core decay heat can be contiauously dissipated up to 15 rercent of rull peye
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conderner as feedvater in the creat generator is converted to stean by heat abso rp tion. Normally, the cap ab ili ty to re tu rn feedenter flov to the ctec3 Ceneratorc is provided by the rain feecwater cj ten.
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