ML16148A247
| ML16148A247 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/01/1979 |
| From: | Noonan V Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16148A248 | List: |
| References | |
| NUDOCS 7906070243 | |
| Download: ML16148A247 (2) | |
Text
MAY 0 1 1979 MEMORANDUM FOR: R. W. Reid, Chief, Operating Reactors Branch No. 4 Division of Operating Reactors FROM:
V. S.,Noonan, Chief, Engineering Branch Division ofOperating Reactors
SUBJECT:
OCONEE NUCLEAR STATION, UNIT 2 - EVALUATION OF THE INSERVICE\\INSPECTION PROGRAM AND RELIEF REQUESTS (TAC 6931)
Plant Name:
Duke. Power Company -.Oconee Unit 3 NSSS Vendor: Babcock & Wilcox Docket Number:
50-270 Responsible Branch and Project Manager: ORB-4, M. Fairtile Engineering & Projects Branch Involved: Engineering Branch Description of Task: Review the Updated Inservice Inspection Program in accordance with the Requirements of 10 CFR 50.55a (g)
Review Status:
Complete In response to your request, the Engineering Branch, Division of Operating Reactors, has reviewed the Inservice Inspection Program submitted by Oconee Nuclear Station, Unit 2. Our safety evaluation for.the inservice inspection program is enclosed. The SER for inservice testing of pumps and valves will be transmitted separately in the near future.
We find the program in compliance to the extent possible with the require ments set forth in Section XI of the 1974 Edition and Addenda through the Summer 1975 of the ASME Boiler and Pressure Vessel Code. We have evaluated requests and granted relief from specific requirements which were determined to be impractical for the facility because of limited access due to design, radiation, geometry and materials of construction of some copponents.
Details of these requests and 4dhe bases for granting or denying relief are given in.the attached evaluation.
We conclude that the Inservice Inspection Progf4m, dated September 21, 1977, plus additional information later submitted by the licensee O
meets the requirements set forth in 10 CFR 50.55a (g) and, therefore, constitutes an acceptable basis for satisying the nquirements of S IE*.
......,1...,............
_____0
NRM(
0240 U.9. GOVaRNMANT PRINTING OFPICE: 1978 - 265 - 769
MAY 0 11979 R.W. Reid
-2 the applicable NRC General Design Criteria, Appendix A, of 10 CFR Part 50.
Originalsigned by&
Vincent S. Noonan, Chief Engineering Branch Division of Operating Reactors
Enclosure:
As, stated
Contact:
C. Y.' Cheng 49-28060 cc: V. Stello, Jr.
R. Mattson D. Eisenhut B. Grimes J. Knight S. Pawlicki R. Gamble M. Fairtile T. Taylor, PNL W. Hazelton G. Johnson I
R. Hermann C. Cheng EB:DOR R
EB:DOR:
h g..
..t.........
.I.
DATE.
NBC FRM 318 (9-76) NRCH 0240 U.s. GOVERNMENT PRINTING OPPICE: 1978 205 709