ML17251A459
| ML17251A459 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/24/1989 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A460 | List: |
| References | |
| NUDOCS 8905010114 | |
| Download: ML17251A459 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 I
I ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AMENDMENT TO F'AGILITY OPERATING LICENSE Amendment No. 35 License No.
DPR-18 l.
The Nuclear Regulatory Commission (the CorrmIission) has found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee),
dated february 16, 1989, complies with
'he 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 faci lity 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.
8905010114 S90424 PDR ADOCK 05000244 P
-'2-2.
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-18 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, 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 7H Richard H. Messman, Director Project Directorate I-3 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 24, 1989
I ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A as follows:
Remove Pa es 4.2-2 Insert Pa es 4.2-2 4.2-3*
- Denotes new page
4.2.1.4 4.2.1.4.a 4.2.1.4.b 4.2.1.5 4.2.1.6 and 2,
0 respectively.
The ins ction program during each third of the first inspection interval provides for examination of all welds at design basis break locations and one-third of all welds at locations where a
weld failure would result in unacceptable consequences.
During each succeeding inspection interval, the program shall provide for an examination of each of the design basis break location welds, and each of the welds at locations where a
weld failure would result in unacceptable consequences.
The inspection intervals for Steam Generator Tubes shall be specified in the "Inservice Inspection Program" for the applicable forty month period commencing with May 1, 1973.
Steam generator tubes that have imperfections greater than 40% through wall, as indicated by eddy current, shall be repaired by plugging or sleeving.
Steam generator sleeves that have imperfections greater than 30% through wall, as indicated by eddy current, shall be repaired by plugging.
Inservice Inspection of ASME Code Class 1,
Class 2 and Class 3 components (Quality Groups A, B and, C) shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been
- granted, by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
The inspection interval for the Inservice Pump and Valve Testing Program shall be ten year intervals commencing with January 1, 1981, 1990 and 2000.
Basis:
The inservice inspection programs provide assurance for the continued.
structural integrity of the structures, components and systems of Ginna Station.
The programs comply with the ASME Boiler and Pressure Vessel Code Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components" as practicable, with due consideration to the design and physical access of the structures, Amendment No.
5
~ 35 4.2-2
Basis (Cont'd) components and compliance will requirements of Part 50 and the CFR Part 50.
systems as manufactured and constructed.
This constitute, an acceptable basis for satisfying the General Design Criterion 32, Appendix A of 10 CFR requirements of Section 50.55a, paragraph g of 10 The repair criteria of 4.2.1.4.a and 4.2.1.4.b are based on the requirements of USNRC Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes" as implemented by RGGE (Reference 1).
This guide describes a method acceptable to the NRC staff for establishing the limiting safe conditions of tube degradation of steam generator tubing.
The repair criteria is based on structural allowances, an allowance for eddy current measurement error and an allowance for degradation during the operating period.
These allowances are added together to determine the repair criteria which is typically 40% for steam generator tubes.
Based on calculations the appropriate sleeve plugging limit is a 42't thru wall defect.
In order to allow for conservatism, a
30% plugging limit for sleeves will be utilized.
Reference 1: "Steam Generator Rapid Sleeving Program Design Uerification Report",
R.E.
Ginna Nuclear Power Plant, August 1982.
Anendnent No.
35 4.2-3