ML19323D273
| ML19323D273 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/07/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323D266 | List: |
| References | |
| NUDOCS 8005210361 | |
| Download: ML19323D273 (8) | |
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[0, UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
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WASHIP4GTON, D. C. 20555 s., -*..../
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54
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License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has 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 1,1977, as supplemented and revised August 17 and September 30, 1977, December 13, 1978 and October 26, 1979, 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 Comission; 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 comon 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.
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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. OPR-50 is hereby amended to read as follows:
(2) Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION sk Yb
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s Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors i
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Attachment:
Changes to the Technical l
Specifications Date of Issuance:
May 7, 1980 i
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T ACH.':ENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
?.evise Appendix A as folicws:
Remove Pa;es Insert Pages 4-11 4-11 4-12 4-12 4-13 4-13 4-13a 4-14 4-14 4-27 deleted Figure 4.2-1 Tns enanges on the revised pages are shown by marginal lines.
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This technien1 specificaticn applies to the inservice inspection of the reacter coolant system pressure boundary and portions of other safety oriented i
system pressure beundaries.
l Objective The objective of this inservice inspecticn program is to provide assurance cf the centinuing integrity of the reacter coclant systsc while at the sa=e time j
mini = icing radiation exposure to persennel in the perfor ance cf inservice i
insp?C* ions.
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Srecification i
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h.2.t Inservice Inspection of ASMI Ccde Class 1, Class 2, and Class 3 cc=penents shall te perfer=ed in accordance with Secticn XI cf the l
ASMI 3ciler and pressure 7essel Ccde and applicable Addenia as
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requirei ty 10 Cy? 50, Sectien 50.55a (g), except where specific written relief has teen granted by the NEO.
L.2.2 The reacter vessel =aterial surveillance capsules re=cved frc= TMI-1 during ICT6 shall be inserted, irradiated in and withdrawn frc= the i
Three Mile islani Unit Uc. 2 reacter vessel in accordance with the
~7 schedule shewn in Table L.2-2.
The licensee shall be respcnsible for the exa=ination of these speci= ens and for sut=ission of repcrts j
of test results in accordance with 10 CFR 50, Appendix H.
i L.2.3 The accessible ;crtiens of cne reactor coclant pu=p =ctor flywheel asse=tly vill te ultrasenically inspected within 3-1/3 years, two within 6-2/3 years, and all fcur by the end of the 10 year inspection interval.
However, the U.T. procedure is developmental and vill te used only to the extent that it is shown to be =eaningful. The extent of ecverage vill te li=ited to those areas of the flywheel which are accessible without =oter disasse=bly, i.e., can be reached i
through the access ports.
Also, if radiation levels at the lover access ports are prohibitive, only the upper access ports vill be used.
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A=endment.No. I3. 29,~54
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L.2. 4 The licencee sha;l sut=it a rep:rt er application for license amendment the !.*EC within 30 da*/s af er the cecurrence of either of the t0 fc11cving:
1.
Failure cf ~hree Idile Island Unit :'o. 2 to achieve ec=ercial operation at 100f, power by October 1,1976, or 2.
Beginning cne year after attainment of ec==ercial operation at 100% pcver, any time that "nree Mile Island Unit No. 2 faile to maintain a cu=ulative reacter utilization factor of at least
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.m TMI-1 with the reacter vessel s =veillance pregra= cenducted at
hree '411e Island Unit :!o. 2, er the applicaticn for license a=end ent shall propese an alternative pregram for conduct for the Di!-1 reacter vessel surveillance progra=.
For the pu pese of this technical specification, the definitien of ec=ercial Operation is that given in Regulatcry ~uide 1.lc, Revision
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Cuculativc reacter utili: ation fa:ter = (Cu~.ulative megawatt
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1005 power x (ICC)) divided by (licensed power (:Gt) x (Cu=ulative hours cince attain ent of cen=ercial cperati.n e.t 1005 power)).
L.2.5 In addition to the reports required by Specificatien h.2.4, a report shall be submitted to the ::.C prior to Septe=ter 1,1952, which su.=arizes *.he first five years of cperating ex;erience with the n.,. -..
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Specifications 4.2.1 & 2 ensure that inservice inspection of ASME Code Class 1, 2 and 3 components vill be performed in accordance with a periodically updated versien of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a (g).
Relief from any of the above require =ents has been provided in writing by the ::KC and is net a part of these technical specificaticas.
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s.r ~ a rea.,cnable uti.'izsti:r of 2II-2, reperting requirements r.re included reevalu9.:icn of t' e program if 2'.I-2 dces not achieve full
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r FC'.'er creraticn in 2 reis:na':le period of ti.e or suffers extended cutages after the first year of c;eratien.
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