ML20151G173
| ML20151G173 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/19/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151G175 | List: |
| References | |
| NUDOCS 8807280182 | |
| Download: ML20151G173 (7) | |
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UNITED STATES
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DUKE POWER C0l!PANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the McGuire Nuclear Station,the facility)
A.
Unit 1 by the Duke Power Company (the licensee) dated May 6,1988, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 conducteri in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 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 Comission's regulations and all applicable requirements have been satisfied.
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.Accordingly, the license is hereby amended by.page changes to'the Technical Specifications as indicated in the attachments to..this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. _ NPF-9.is hereby amended to read as follows:
(2)'TechnicalSpecifications The Technical Specifications contained in Appendix.A, as revised through Amendment No. 89, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0fEISSION Original signed by:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of Issuance:
July 19, 1988 A
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DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMEllDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the McGuire fiuclear Station,the facility) Fa A.
Unit 2 i
by the Duke Power Company (the licensee) dated May 6,1988, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 ecmplian;e with the Comission's regulations set forth in 10 CFR Chapter I; 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..the license is hereby amended by page changes to the Technical t
' Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby.
amended to read as follows:
(2)-Techn'icalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, are hereby incorporated into the. license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan..
3.
This license amendment. is effective as of its date of issuance.
FOR THE llUCLEAR REGULATORY COMMISSION Original signed by:
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II-
Attachment:
Technical Spar.ification Changes Date of Issuance:
July 19, 1988 0FFICIAL RECORD COPY EF}TDG OG(rM C IPh[1;)-3 O
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- ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET N0. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 4-14 3/4 4-15
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x REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this specification:
1)
Imperfection means an exception to the dimensions, finish or contour of a tube fror that requirea by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be consid-ered as imperfections; 2)
Cegradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube; 3)
Degraded Tube means a tube containing imperfections greater than or equal to RO% of the nominal wall thickness caused by degradation; 4)
% degradation means the percentage of the tube wall thickness affected or removed by degradation; 5)
Defect means an imperfection of such severity that it exceeds the plugging limit.
A tube containing a defect is defective; 6)
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness.
This definition does not apply to the area of the tubesheet region below the F* distance pro-vided the tube is not degraded (i.e., no indications of crack-ing) within the F* distance.
7)
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integ-rity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c, above; 8)
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg; and McGUIRE - UNITS 1 and 2 3/4 4-14 Amendment No. 89 (Unit 1)
Amendment No. 70 (Unit 2)
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9)
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a basel1ne condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
10)
F* Distance is the distance into the tubesheet from the top face of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively chosen to be 2 inches.
11)
F* TUBE is a tube with degradation equal to or greater than 40%,
below the F* distance and not degraded (i.e., no indications of cracking) in the F* distance, b.
The steam generator shall be determined OPERABLE after completing the
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corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.
4.4.5.5 Reports a.
Within 15 days following t'1e completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; b.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1)
Number and extent of tubes inspected, 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identification of tubes plugged, c.
The results of inspections of F* tubes shall be reported to the Commission in a report, prior to the restart of the unit following l
the inspection.
This report shall include:
1)
Identification of F* tubes, and 2) location and size of the degradation.
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McGUIRE - UNITS 1 and 2 3/4 4-15 Amendment No. 89 (Unit 1)
Amendment No. 70 (Unit 2)
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