ML20211K162
| ML20211K162 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/24/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-58000, NUDOCS 8606270339 | |
| Download: ML20211K162 (3) | |
Text
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June 24, 1986 G'4 7
h Docket No. 50-285 Distribution: &acket Files )
NRC & L PDRs
%raDTE'i. 3a PD#8 Reading LHarmon OELD ACRS 10 EJordan JPartlow BGrimes PKreutzer Mr. R. L. Andrews FMiraglia DSells Division Manager - Nuclear Production ORAS TBarnhart Omaha Public Power District OPA LFMB 1623 Harney Street WJones EButcher Omaha, Nebraska 68102 NThompson/DHFT DCrutchfield WRegan YCheng
Dear Mr. Andrews:
SUBJECT:
USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE CASE N-408 FOR FORT CALHOUN STATION, UNIT NO. 1 By letter dated June 17 and October 15, 1985 and January 20 and March 12, 1986 you requested authorization to apply ASME Code Case N-408, " Alternative Rules for Examination of Class 2 Piping,Section XI, Division 1,"
at the Fort Calhoun Station, Unit No. 1.
Code Case N-408 has been endorsed by the NRC and is referenced in Revision 4 of Regulatory Guide 1.147, " Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1", dated September 1985.
The staff has reviewed your request and determined that Code Case N-408 is an acceptable Code Case which is approved as written except for conditions regarding Preservice Inspection as described in the subject Regulatory Guide.
Since these conditions do not apply to Fort Calhoun Station, Unit No. 1, Code Case N-408 may be used with the limitations stated in the " Inquiry" and
" Reply" sections of the Code Case.
This conclusion is based uoon our determination, pursuant to 10 CFR 50.55a(a)(3), that the licensee has demonstrated that the inservice inspection of piping embedded in concrete that is exposed to no water, no temperature greater than containment ambient, and no pressure greater than containment ambient (exclusive of a LOCA or main steam line break) would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Sincerely, Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B cc:
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NRC & L PDRs Branch File 3.3a PD#8 Reading LHarmon OELD ACRS 10 EJordan JPartlow BGrimes PKreutzer Mr. R. L. Andrews FMiraglia DSells Division Manager - Nuclear Production ORAS TBarnhart Omaha Public Power District OPA LFMB 1623 Harney Street WJones EButcher Omaha, Nebraska 68102 NThompson/DHFT DCrutchfield WRegan YCheng
Dear Mr. Andrews:
SUBJECT:
USE OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE CASE N-408 FOR FORT CALHOUN STATION, UNIT NO. 1 By letter dated June 17 and October 15, 1985 and January 20 and March 12, 1986 you requested authorization to apply ASME Code Case N-408, " Alternative Rules for Examination of Class 2 Piping,Section XI, Division 1,"
at the Fort Calhoun Station, Unit No. 1.
Code Case N-408 has been endorsed by the NRC and is referenced in Revision 4 of Regulatory Guide 1.147, " Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1", dated September 1985.
The staff has reviewed your request and determined that Code Case N-408 is an acceptable Code Case which is approved as written except for conditions regarding Preservice Inspection as described in the subject Regulatory Guide.
Since these conditions do not apply to Fort Calhoun Station, Unit No. 1, Code Case N-408 may be used with the limitations stated in the " Inquiry" and
" Reply" sections of the Code Case.
This conclusion is based upon our determination, pursuant to 10 CFR 50.55a(a)(3), that the licensee has demonstrated that the inservice inspection of piping embedded in concrete that is exposed to no water, no temperature greater than containment ambient, and no pressure greater than containment ambient (exclusive of a LOCA or main steam line break) would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Sincerely Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B cc:
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Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District Unit No. 1 i
cc:
Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Metropolitan Planning Agency ATTN:
Dagnia Prieditis 7000 West Center Road Omaha, Nebraska 68107 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue I
Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
.