ML20057A657
| ML20057A657 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/30/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A655 | List: |
| References | |
| NUDOCS 9309150110 | |
| Download: ML20057A657 (3) | |
Text
,
~.
/
'o UNITED STATES i
't NUCLEAR REGULATORY COMMISSION
.g
- p WASHINGT ON, D. C. 20$55
%w....+f i
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXEMPTION FROM APPENDIX J TO 10 CFR PART 50 i
AND TO AMENDMENT N0.196 TO FACILITY OPERATING LICENSE NO. OPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i
i
1.0 INTRODUCTION
By letter dated June 28, 1993, the Power Authority of the State of New York l
(the licensee) submitted a request for changes to the James A. FitzPatrick l
Nuclear Power Plant, Technical Specifications (TSs). The requested changes i
would revise TS 4.7.A.2.f to eliminate the requirement to perform a Type A,_B, i
or C leak rate test following the completion of planned repairs to sections of the Core Spray system minimum flow lines during the fall 1993 maintenance outage. The licensee's submittal of June 28, 1993, also requested a one-time exemption from the requirements of Section IV.A. of Appendix J to 10 CFR l
Part 50. The one-time exemption _ concerned the requirement to perform a i
Type A, B, or C leak rate test following the completion of the Core Spray system minimum flow line repairs.
2.
EVALUATION i
The licensee discovered the presence of pipe wall thinning in the two Core Spray system minimum flow lines (3"-W23-152-7A, B) as a result of augmented i
erosion / corrosion inspections that were conducted during the 1992 refueling l
outage. The wall thinning was attributed to cavitation-induced pitting due to the location of the restricting orifice in each of these lines.
In view of the inspection findings, the licen.ee intends to replace approximately 5 feet
~
of piping in each of these lines during the fall 1993 maintenance outage.
This 3-week outage is scheduled for September 1993. The sections of piping to be replaced include the restricting orifices (14R0-27A, B)~ and the Core Spray minimum flow valves (14MOV-5A/58). The planned repair constitutes a replacement of a component that is part of the primary containment boundary and would be performed in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, and American National standards Institute (ANSI) B31.1-1967 (the construction Code i
for the facility).-
Section IV.A of Appendix J to 10 CFR Part 50, requires that a Type A, B, or C test (as applicable) be performed following any major modification or repair of a component which is part of the primary containment boundary. The 9309150110 930830 DR ADOCK 0500 3-
~
. licensee has determined that the requirement to conduct a Type A, B, or C test following repairs is applicable to replacement of the sections of the Core Spray system minimum flow lines.
However, because of the locations of the repairs, a Type B or C test cannot be performed.
In addition, because of the setup and testing time involved and the significant delay it would cause on plant startup, a Type A primary containment integrated leak rate test is not practical. The licensee estimates that performance of a Type A test would extend the planned 3-week outage by a minimum of 3 to 4 weeks.
In lieu of a Type A, B, or C test, the licensee has proposed an alternate inspection program, including 100 percent radiography of the new welds, surface examination on new welds that form a portion of the primary containment boundary, and a system leakage test (in accordance with ASMF Code,Section XI, 1980 Edition through Winter 1981 Addenda, paragraph IWA-5213) to ensure structural integrity and leak tightness. The staff has reviewed the licensee's alternate testing program and concluded that these nondestructive examinations will meet the intent of Section IV. A. of Appendix J to 10 CFR Part 50, which is to assure that modifications to the containment pressure boundary are leak tight. The licensee has stated that they will perform a Type A test during the next refueling outage that is currently scheduled to start in January 1995.
3.0
SUMMARY
On the basis of the testing that will be performed by the licensee to ensure the adequacy of repairs to the Core Spray system minimum flow lines, and in consideration of the problems involved with performing a leak rate test, and in recognition that the repairs and subsequent testing will be performed in accordance with the applicable ASME and ANSI Codes, the staff concludes that the requested one-time exemption from the testing requirements of Section IV.A. of Appendix J to 10 CFR Part 50 is acceptable.
In addition, the requested change to TS 4.7.A.2.f is also acceptable since it merely reflects in the TSs the provisions of the one-time exemption.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The state official had no comments.
5.0 ENVIRONMENTAL CONSIDEPATION The amendment changes a requirement with respect to installation or use of a facility component located eithin the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation
l I i exposure. The Commission has previously issued a proposed finding that the l
amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR 39060). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
For the Exemption, pursuant to 10 CFR 51.21, 51.32, and 51.35, an I
environmental assessment and finding of no significant impact was published in the Federal Reaister on August 5, 1993 (58 FR 41812).
Accordingly, based upon the environmental assessment, the NRC staff has determined that issuance of this amendment will not have a significant effect on the quality of the human environment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) these is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
J. Menning Date:
Nmmt 30, 1o43 l
)
t j
i
.r->
-