ML17164A522
| ML17164A522 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/09/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17164A523 | List: |
| References | |
| TAC-M83342, NUDOCS 9501180269 | |
| Download: ML17164A522 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMM(SSION WASHINGTON, D.C. 2055&4001 January 9, 1995 Mr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
SUBJECT:
EVALUATION OF THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN, REVISION 2, AND ASSOCIATED REQUESTS FOR RELIEF FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNIT I (TAC NO. M83342)
Dear Mr. Byram:
The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the information provided by Pennsylvania Power 5 Light Company (PPEL) in a letter dated April 21,
- 1992, and addition information provided by PP8L in letters dated September 7,
- 1993, and February 22, 1994.
PPEL's submittals are related to Revision 2, of the Susquehanna Steam Electric Station, Unit I first ten-year inservice inspection program plan, and associated requests for relief from the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, which were made pursuant to 10 CFR 50.55a(g)(5).
Based on the information submitted, the staff adopts the contractor's conclusions and recommendations presented in the enclosed Technical Evaluation Letter (Enclosure
- 2) with the exception of Request for Relief Nos.
IRR-11 and IRR-19 concerning less than essentially 100X volumetric examination of one RPV shell weld.
To complete the evaluation of RR-II, additional information is required regarding alternatives to the regulatory requirements contained in 10 CFR 50.55a(g)(6)(ii)(A).
Request No. IRR-19 concerns augmented examination of Class 2 piping in accordance with the Final Safety Evaluation Report and does not require relief from the ASME Code.
The staff approves the licensee's proposal regarding these examinations.
As discussed in the safety evaluation (Enclosure I), the Commission has concluded that certain Code requirements are impractical based on limited accessibility, or hardship based on hardware configurations and geometry.
Compliance with the code would require the redesign or replacement of the affected component.
Accordingly, the staff, is hereby granting relief and imposing alternative examinations where noted for Requests for Relief IRR-12 (in part),
IRR-13, IRR-14, IRR-15 (in part),
IRR-16, IRR-I7, IRR-18, and IRR-20 (in part).
The relief granted is authorized by law pursuant to 10 CFR 50.55a(6)(i) and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. for Request for Relief IRR-15 (in part), the requirements of the Code have been met and relief is not required.
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Byram For Requests for Relief 1RR-12 (in part) and for Request for Relief 1RR-20 (in part) relief was not required.
Relief 1RR-21 was withdrawn from the program by the licensee.
Sincerely,
/s/
John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No:
50-387
Enclosures:
As stated cc w/encls:
See next page DISTRIBUTION I y.. Docket-Fi-le PUBLIC PDI-2 Reading WRussel l/FMiragli a RZimmerman RSpessard, JLieberman SVarga/JZwolinski JStolz CPoslusn MO'Brien OPA OGC OC/LFDCB EJordan
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Byram For Requests for Relief 1RR-12 (in part) and for Request for Relief 1RR-20 (in part) relief was not required.
Relief 1RR-21 was withdrawn from the program by the licensee.
Sincerely, Docket No:
50-387
Enclosures:
As stated cc w/encls:
See next page o
S olz, Direc or Pr ject Directorate I-2 ivision of Reactor Projects I/II Office of Nuclear Reactor Regulation
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Mr. Robert G.
Byram Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.
M. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harr isburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Vice President-Nuclear Operations Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803