ML20084C767
| ML20084C767 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/09/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML19280D931 | List: |
| References | |
| DPR-50-A-091 NUDOCS 8404300266 | |
| Download: ML20084C767 (4) | |
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UNITED STATES y })
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NUCLEAR REGULATORY COMMISSION
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by GPU Nuclear Corporation, et al-(the licensees) dated May 9, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, Facility Operating License No. DPR-50 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Revise paragraph 2.C.(2) to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, are hereby incorporated in the license.
The GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGyCATORYCOMMISSION
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- W J 'NG John F. Stolz, Chief '
erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 9,1984 d
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of cha'nge.
Remove Insert 4-81 4-81
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b.
The steam generator shall be determined OPTRABLE after completing the corresponding actions (removal from service by plugging, or repair by the kinetic expansion process *, of all tubes exceeding the repair limit and all tubes containing throu;;nwall cracks) required by Table 4.19.2.
4.19.5 F.eoort s a.
Following the completion of each inservice inspection of steam generator tubes, the number of tubes repaired or removed from service in each steam generator shall be reported to the NRC within 15 days.
b.
The complete results of the steam generator tube inservice inspection shall be reported to the NRC within 3 months following completion of the inspection. This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-chickness penetration for each indication of an imperfection.
3.
Identification of tubes repaiVed or removed from service.
c.
Raoults of steen generator tube inspections which fall into Category C-3 and require prompt notification of the NRC shall be reported pursuant to Specification 6.9.2 prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Bases The Surv=411=^e Requirements for inspection of the steem generator tubes ensure that the structural integrity of this portion of the RCS will be maintained.
4-81
- The phrase "or repair by the kinetic expansion process" shall be in effect only during the period of ore-critical hot functional testina.
l Amendment No. 47, SJ,91 P
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