ML17340B036

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Amends 64 & 56 to Licenses DPR-31 & DPR-41,respectively, Updating Tech Spec 4.2-1(7.1),reactor Coolant Pump Flywheel Inservice Insp,To Conform W/Reg Guide 1.14,Section XI of ASME Code & SRP
ML17340B036
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 04/16/1981
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17340B037 List:
References
NUDOCS 8104230244
Download: ML17340B036 (10)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

64 License No.

DPR-31 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power and Light Company (the licensee) dated March 5, 1981, 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 Commission'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.

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4'4 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.

DPR-31 is hereby amended to read as follows:

(B)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, 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 NUCLEAR REGULATORY COMMISSION i

'C ve

arga, Chief Operating React s Branch No.

1 Division of Licensing

Attachment:

Changes to the'echnical Specifications Date of Issuance:

April 16, 1981

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+~*~4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.

4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

56 License No.

DPP,-41 l.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

The application for amendment by Florida Power and Light Company (the licensee) dated March 5, 1981, complies wit'h the. standar'ds and requirements of the Atomic'nergy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.

DPR-41 is hereby amended to read as follows:

(8)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.

56, 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 i".s issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 5

e en A. Var a, Qief'perating Reactors48ranch No.

1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 16, 1981

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

64 TO FACILITY OPERATING LICENSE NO: DPR-31 AMENDMENT NO.

56 TO FACILITY OPERATING LICENSE NO.

DPR-41 DOCKET NOS.

50-250 AND 50-251 Revise Appendix A as follows:

Table 4.2-1 (continued)

(Item No. 7.1)

Insert Pa es Table 4.2-1 (continued)

(Item No. 7.1)

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TABEE 4 2-l COHTIHUED Item Ho.

Examination CatL+~or Extent of Examination Components cnd Parts (Percent in 10 Year To be Examined Hcthod Interval)

Extent of Examination Percent in 5 Year Interval)

Remarks 6 ~ 5 0-2 Prcssure-retaining bulb Visual and lOOX Voluma trio

33X, Exception is taken for valves uhich are not accessible; 6,6 6.7

- E-2 Integrally-uoldcd supper'ta Supports and Hangers Visual Hot Applicnblc lOOX Hot Applicable 33X Exception is taken for supports and hangers

~uhich are not accessible.

7 ~ I Reactor coolant pump flyuheel 100X(2)

In-place at bore Insorvice inspection shall be performed on and keyuay (l)

. each reactor coolant pump flyuheel during the refueling or maintenance shutdoun poinciding uith the In-Service Inspection schedule as required by Section XI of thc AHSE Boiler ond Pressure Vessel Codes (l) An in-plapc ultrasonic volumetrip examination of thc area of higher stress gonpcntration at rho boro and kcyway at approximately 3-year intervals, (2) A surface examination of all exposed surfaCes cnd complete ultrasonic examination at or near tbe cnd of each 10-year interval.

7.2 Irradiation Specimcnt Schedule Tensile and Charpy V

Hotch (Madge Open l.oadiug)

See Remarko See Remarks Capsule I shall be removed cnd examined at thc first region replacement.

Capsule 2

shall be removed and examined at the fourth region roplnccmcnt, Capsule 3 shall bc removed nnd examined after tucnty years of operation.

Capsule 4 shall bc rcmovcd and cxamin<<d after thirty years of operation.

Capsule 5 shall be removed and examined after forty years of operation.