ML19262A427
| ML19262A427 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/16/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19262A422 | List: |
| References | |
| NUDOCS 7910290518 | |
| Download: ML19262A427 (6) | |
Text
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1 UNITED STATES r
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,1 NUCLEAR REGULATORY COT.i'.*lsslON j.$ %
j WASHtNGTON, D. C. 20555 i
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n.: y METROPOLITAi! EDISON C0!iPAt1Y JERSEY CENTRAL POWER AtlD LIGHT COMPAtlY PENNSYLVANIA ELECTRIC C0ftPAtlY DOCKET fl0. 50-289 e
THREE MILE ISLAND flVCLEAR STATION, UtlIT NO. 1 AMENCMENT TO FACILITY OPERATIrlG LICEtlSE Amendment flo.42 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Metropolitan Ediscn Company, Jersey Central Power and Light Company and Pennsylvann Electric Company (the licensees), dated February 3,1978, as supplemented April 10, and July 7,1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, 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 Comnission's regulations; 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 Commission's regulations and all applicable requirements have been satisfied.
1484 169 7910290 N
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follws:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment tio. 42, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE fiUCLEAR REGULATORY C0fEISSION
,,/fy
? &m:
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 16, 1978 4
1484 170
ATTACHME?lT TO LICEtlSE Af!Et1DMEllT ?!0. 42 FACILITY OPEPATIflG LICEf!SE fl0. OPR-50 DOCKET fl0. 50-289 Revise Appendix A as follows:
Remove Paces Insert Pages 11 ii 3-18b 4-59 4-59 The changes on the revised pages are shown hy marginal lines.
1484 171
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I 3.1.11 REACTOR I::TIR !ALS VI:.7 VALVES Aeolicability
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Applies to Reactor Internals Vent Valves 1
Objective To verify that no reactor internals vent valve is stuck in the open positica and that each valve continues to exhibit freedes of =cve=ent.
Seeci ficatiens 3.1.11.1 The structural integrity and operability of the reacter internals vent valves shall be maintained at a level censistent with the acceptance criteria in Specification k.16.
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4.16 REACTOR I: ITER:!ALS VE!T VALVES SGVE!LLAI;CE.
Apolienbilitv Applies to Reactor Internals Vent Valves.
Objective To verify that no reactor internals vent valve is stuck in the open position and that each valve continues to exhibit freedes of =ovement.
1
' Snecificatien Frecuency Item Test h.16.1 Reactor Internals De=enstrate Operability Each refueling shutdown.
Vent Valves By:
a.
Conducting a remote visual inspection of visually accessible sur-faces of the valve body and disc sealin6 faces and evaluating any observed surface irregu-larities.
b.,
Verifying that the valve is not stuck in an open position, and c.
Verifying thrcugh manual actuation that the valve is fully open with a force of < h00 lbs (applied vertically upward).
Bases flev dces not Verifying vent valve freedcm of movenent insures that coolant bypass the core through reacter internals vent valves during operaticn and therefore incures the censervatism of Core Protection Safety li=its as de-lineated in figure: 2.1-1 and 2.1-3, and the flux / flew trip setpcint.
4-59 1484 174