ML19290A384
| ML19290A384 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/16/1974 |
| From: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19290A383 | List: |
| References | |
| NUDOCS 7911060622 | |
| Download: ML19290A384 (4) | |
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- e UNITED STATES g
ff N. M
- ATOMIC ENERGY COMMISSION Ib
- wassisoTon, o.c. zos4s I *1 Yj METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPAN DOCKET NO. 50-289 (Three Mile Island Nuclear Station, Unit 1)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. DPR-50 1.
The Atomic Energy Commission (the Commis: ion) 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 July 17, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the Conmission's rules and regulations; 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 Conmission's regulations; D.
The issuance of this amendment will not be inimical to the conmon 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 No. OPR-50 is hereby amended to read as follows:
1556 250 06o 6E
, 911
. "(2) Technical Scecifications The Technical Specifications contained in Appendices A and B attached to Facility Operating License No. DPR-50 are revised as indicated in the attachment to this license amendment.
The Technical Specifications, as revised, are hereby incor-porated 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 July 12, 1974.
FOR THE ATOMIC ENERGY COMMISSION orfrisal signed by You A Mum Voss A. Moore, Assistant Director for Light Water Reactors, Group 2 Directorate of Licensing
Attachment:
Change No. 3 to Appendix A Technical Specifications License No. DPR-50 Date of Issuance:
AUG 161974 1556 251
Amendment No. 4 Change No. 3 TURBINE ~ CYCLE Applicability Applies to the operating status of the turbine cycle when fuel is in the core and the capability of the decay removal system is exceeded.
Objective To specify minimum conditions of the turbine cycle steam relieving capacity and emergency feedwater pumps to ensure capability to remove decay heat equivalent to five percent of full power.
Specification The reactor coolant system shall not be heated above 250 F with irradiated fuel in the core unless the following conditions are met:
3.4.1 Four of the six turbine bypass valves are operable.
3.4.2 The turbine driven emergency feedwater pump and two half-sized motor-driven emergency feedwater pumps shall be operable.
3.4.3 A minimum of 150,000 gallons of condensate is available in each condensate storage tank.
3.4.4 System piping and valves, directly associated with the above components are operable.
3.4.5 Any component cited above may be removed 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.
3.4.6 All eighteen main steam safety valves shall be operable or, if any are not operable, the maximum overpower trip setpoint (see Table 2.3-1) shall be reset as follows:
Maximum Number of Maximum Overpower Safety Valves Disabled On Trip Setpoint Any Steam Generator
(% of Rated Power) 1 92.4 2
79.4 3
66.3
- 0peration with more than three safety valves disabled on any steam generator is not permitted.
Date of Issuance: c"1 16 574 3-25 1556 252
Amendment No. 4 Change No. 3 Bases Norr.al A reactor shutdown from power requires removal of core decay heat.
decay heat removal is by the steam generator with the steam dump to the con-denser when system temperature is above 250*F and by the decay heat removal Therefore, core decay heat can be continuously system below 250'F.
dissipated up to 15 percent of full power via the steam bypass to the con-denser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the capability to return feedwater flow to the steam generators is provided by the main feedwater system.
1556 253 Date of Issuance:
AUG 1 6 N 4 3-25a
UNITED STATES ATOMIC ENERGY COMMISSION DOCKET N0. 50-289 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY NOTICE OF ISSUANCE OF FACILITY LICENSE AMENDMENT Notice is hereby given that the U. S. Atomic Energy Comission (the Comission) has issued Amendment No. 4 to Facility Operating License No. DPR-50 issued to Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company, for operation of Three Mile Island Nuclear Station, Unit 1, located in Dauphin County, Pennsylvania. The amendment is effective as of July 12,19/4.
The amendment sets operating power limits for the plant when steam safety valves are not operable. This amendment relates to radiological safety matters previously considered but does not involve a significant hazards consideration.
For further details with respect to this action, see (1) the licensees' letter dated July 17,1974, and (2) the Commission's related Safety Evaluation, dated July 12, 1974. These are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., Washington, D. C., and at the Government Publication Section, State Library of Pennsylvania, Box 1601 (Education Building), Harrisburg, Pennsylvania. A copy of item (2) may be obtained upon request addressed to the United States Atomic Energy Comission, Washington, D. C.
20545, Attention:
Deputy Director for Reactor Projects, Directorate of Licensing - Regulation.
1556 254 v u t.nt us Dated at Bethesda, Maryland, this AUG 1 6 W 4 FOR THE ATOMIC ENERGY COMMISSION ortdnafsiskV
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A. Schwencer, Branch Chief Light Water Reactors Branch 2-3 Directorate of Licensing 1556 255