ML20211J343
| ML20211J343 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/01/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211J349 | List: |
| References | |
| NUDOCS 9909030124 | |
| Download: ML20211J343 (7) | |
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- [ps l*i UNITED STATES e-2'Y S
NUCLEAR REGULATOR'.' COMMISSION f
WASHINGTON. D.C. 20555-0001
.....p BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 231 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 30,1999, as supplemented May 25,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, a 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.
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-53 is hereby amended to read as follows:
9909030124 990901 1
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2-2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 231, 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 and shall be implemented during the spring 2000 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
,W S. Singh Bajwa, Chief, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifical;ons Date of issuance:
September 1, 1999 1
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 207-License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 30,1998, as supplemented May 25,1999, 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;
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j 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)
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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 i
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 2.C.2. of Facility Operating License No. DPR-69 is hereby amended to read as follows:
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. 2.
Technical Specifications 1
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 207., 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 and shall be implemented during the spring 2001 refueling outage.
FOR THE NUC' EAR REGULATORY COMMISSION nb#
a S. Singh Bajwa, Chief, Section 1 Project Directorate I
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Division of Licensing Project Management Office of Nuclear Reactor Regulation I
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 1, 1999.
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ATTACHMENTTO LICENSE AMENDMENTS AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. DPR 53 AMENDMENT NO. 207 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The. revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Paaes insert Paaes 5.0-18 5.0-18 5.0-19 5.0-19 l
4
Programs and Manuals 5.5 5.5 Programs and Manuals 5.
% Dearadation means the percentage of the tube wall thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube containing a defect is defective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.
7.
Pluaaina or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging, or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection. The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:
1.
original. tube wall 40%
ii. Westinghouse laser welded sleeve wall 40%
iii. ABB-Combustion Engineering leak tight sleeve wall 28%
iv. ABB-Combustion Engineering Alloy 800 leak-limiting sleeve wall 35%
8.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 5.5.9.c.3 above.
9.
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.
I CALVERT CLIFFS - UNIT 1-5.0-18 Amendment No. 231 CALVERT CLIFFS - UNIT 2 Amendment No. 207
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Programs and Manuals 5.5 5.5 Programs and Manuals
- 10. Tube boair refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following processes:
1.
Westinghouse Laser Welded Sleeving as described in the proprietary Westinghouse Reports WCAP-13698, Revision 2 " Laser Welded Sleeves for 3/4 Inch Diameter Tube Feedring-Type and Westinghouse Preheater Steam Generators, Generic Sleeving Report," April 1995; and WCAP-14469, " Specific Application of Laser Welded Sleeving for the Calvert Cliffs Power Plant Steam Generators,"
November 1995, ii. ABB-Combusting Engineering Leak Tight Sleeving as described in the proprietary ABB-Combustion Engineering Report CEN-630-P, Revision 01, " Repair of3/4"0.D.SteamGeneratorTubesUsingLeakTight Sleeves," August 1996. A post-weld heat treatment during installation will be performed.
iii. ABB-Combustion Engineering Alloy 800 leak-limiting sleeving as described in the Proprietary ABB Combustion Engineering Report CEN-633-P, Revision 03-P, " Steam Generator Tube Repair For Combustion Engineering Designed Plants with 3/4.048InchWallInconel600TubesUsingLeak Limiting Alloy 800 Sleeves, " October 1998.
Tube repair includes the removal of plugs that were previously installed as a corrective or preventive measure. A tube inspection per 5.5.9.d.9 is required prior to returning previously plugged tubes to service.
e.
Surveillance Completion - The Steam Generator Tube Surveillance Program is met after completing the corresponding actions (plug or repair all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Tables 5.5.9-2 and 5.5.9-3.
CALVERT CLIFFS - UNIT 1 5.0-19 Amendment No. 231
-CALVERT CLIFFS - UNIT 2 Amendment No. 207