ML17251A461
| ML17251A461 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/24/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A460 | List: |
| References | |
| NUDOCS 8905010116 | |
| Download: ML17251A461 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR RFACTOR REGULATION SUPPORTING AMENDMENT NO.
35 TO FACILITY OPERATING LICENSE NO.
DPR-18 ROCHESTER GAS AND EI.FCTRIC CORPORATION R.
E.
GINNA'UCLEAR POWER PLANT DOCKET NO. 50-244
- 1. 0 INTRODUCTION By letter dated February 16, 1989, Rochester Gas 5 Electric Corporation proposed changes to Technical Specifications (TS) 4.2-2 for the Ginna Nuclear Power Plant.
The proposed changes would add quantitative requirements for resleeving and plugging of steam generator tubes.
These criteria are presently required in the plant Quality Assurance (QA) manual.
2.0 BACKGROUND
On July 19, 1988, the NRC staff met with representatives from Rochester Gas 5
Electric Corporation (RG&E) and its consultants from Combustion Engineering to discuss steam generator sleeving utilizing a new technique for sleeve installation.
(See NRC letter to RGRE dated December 1, 1988).
The purpose of the meeting was for RGSE to describe the development program which would result in a sleeve design and necessary tooling to service currently inaccessible areas of the steam generators such that as much as 95K of the steam generators could be resleeved for extended service life.
Additionally, the NRC staff suggested the benefits of including steam generator tube sleeving and plugging requirements in the plant TS.
The licensee agreed and submitted an amendment request to their license.
- 3. 0 EVALUATION The proposed additions to the technical specifications are as follows:
l.
4.2.1.4.a - Steam generator tubes that have imperfections greater than 40K throughwall, as indicated by eddy current, shall be repaired by plugging or sleeving.
4.2.1.4.b - Steam generator sleeves that have imperfections greater than 30K throughwall, as indicated by eddy current, shall be repaired by plugging.
3.
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 pp01011 05000244 6 890424 PDR ADOCK p
Degraded PWR Steam Generator Tube's,"
as implemented by RGAE (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 40Ã for steam generator tubes.
Based on calculations the appropriate sleeve plugging limit is a 42K throughwall defect.
In order to allow for conservatism, a
30K plugging limit for sleeves will be utilized.
The licensee's proposed changes to its technical specification are administra-tive in nature and are consistent with other PWR TS.
The change would add the same requirements that currently exist in the plant guality Assurance manual to the plant technical specifications.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in recordkeeping, or administrative procedures or requirements because the same requirements that currently exist in the plant guality Assurance Manual are being added to the plant Technical Specifications.
The Commission has previously issued a proposed finding that this amendment involves no signficant hazards consideration and there has been no public comment on such finding.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
- 5. 0 CONCLUSION The Commission made a proposed determination that the amendment involves no significant hazards consideration, which was published in the Federal Register 84pR])942
) on March 22, 1989.
The Commission consulted with the State of New York.
No public comments were received, and the State of New York did not have any comments.
On the basis of the consideration discussed
- above, the staff concludes that (1) there is reasonable assurance that the health and'afety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
C. Stahle, D. Solorio Dated:
April 24, 1989