ML19270H519
| ML19270H519 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/04/1974 |
| From: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19210B193 | List: |
| References | |
| NUDOCS 7911040122 | |
| Download: ML19270H519 (3) | |
Text
.
UNITED STATES f
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ATOMIC ENERGY COMMISSION l 1.1%p e['
WASH INGToN. O.C.
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL PCUER AD LIGHT COMPANY PENNSYLVA'!IA ELECTRIC COMPANY DOCKET NO. 50-289 (Three Mile Island Nuclear Station, Unit 1)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. DPR-50 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for amendment by Metropolitan Edison Company, Jowey Ceuu ol Tv et a nd L ir,In. Cumpouy Feuudylvania anu 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 Commission's rules and regulationc set forth in 10 CFR Cha g er I; E
The facility will operate in conformity with the license, the provisions of the Act, and the rules and regulations of the Co= mission; C.
There is reasonable assurance (1) 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 ufil not be inimical to the common defense and security or to the health and safety of the public; and E.
Prior public notice of this amendrent is not required since the amendment does not involve a significant hazards consideration.
2.
Accordingly, Paragraph 2.C.(2) of Facility License No. DPR-50 is.
hereby amended to read as follows:
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Amendment No. 2 Change No. 2 TURBINE CYCLE Applicability Applies to the operating status of the turbine cycle when fuel is in the e
core and the capability of the decay removal system is exceeded.
Objective To specify minimum conditions of the turbine cycle steam relieving capacLty and emergency feedwater pumps to ersure capability to remove decay heat equivalent to five percent of full power.
Specification The reactor coolant system shall not be heated above 250*F unless the following conditions are met:
3.4.1 Eighteen main steam valves shall be operable.
3.4.2 Four of the six turbine by-pass valves are operable.
3.4.3 The turbine driven emergency feedwater pu=p and two half-sized motor-driven emergency feedwater pumps shall be operable.
3.4.4 A =ini=us of 150,000 gallons of condensate available in the condensate utorage tanks.
3.4.5 System piping and valves, directly associcted with the cbove components operable.
3.4.6 Any component in 3.4.3 or 3.4.5 above may be re_oved from service for purposes of maintenance for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
If this period is exceeded the unit will 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 emergency feedwater pumps required by 3.4.3 may be removed from service for maintenance indefinitely provided 2
that the reactor has never been or erated at greater than 57' of rated thermal power.
Bases A reactor shutdown from power requires renoval of core decay heat. Normal decay heat removal is by the steam generator with the steam dump to the condenser when system temperature is above 250*F and by the decay heat removal system below 250*F.
Therefore, core decay heat can be continuously dissipated up to 15 percent of full power via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorptior.. Normally, the capability to return feedwater flow to the stear. generators is provided by the main feedwater syst2m.
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Date of Issuance: ;';u 4
- pg 3-25
. greater than one-half of the design value, which is conservatively based on the assumption that the plant is shut down after continuous operation at full power. Therefore, if the plant power level has never been allowed to exceed even 5% of rated power, the decay heat load can never be beyond the delivery capacity of any one EFU pump, and any two of these pumps provide a fully redundant emergency feedwater supply.
This reduced power aspect of the EFW System was considered in the original licensing review of TMI-1 and was addressed explicitly in Amendment No. 1 to this license which was issued on May I',1974.
In that Amendment, consideration was given only to unavailaoility of one of the motor-driven pumps; it would have been valid there to include the turbine-driven pump.
Conclusion The staff concludes that the Technical Specification change proposed by Meted in their June 3, 1974 letter does not:
(1) involve a safety consideration of a type or magnitude not con-sidered by any previous staff safety review of this facility, (2) potentially involve a substantial increase in the probability ar c;..ac3 c.mu.
vi au accident consieured in any previous start safety review, or (3) potentially decrease the margin of safety during normal plant operation, anticipated operational occurrences or postulated accidents considereu in any previous staff safety review.
Based on the foregoing analysis, the staff finds that there is reasonable assurance that the health and safety of the cublic will not be endangered by approval of the change to Technical Specification 3.4.7 as proposed by Meted.
/17
[,Y,l, p.ww C ' f 'l R. M. Bernero, Project Manager Light Uater Reactors Branch 2-3 Directorate pf Licensing n
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A. Schwencer, Chief Light Uater Reactors Branch 2-3 Directorate of Licensing 7CcJ) o 7 7. q Date of Issuance: f9 !
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