ULNRC-05291, Correction to Authorization of Relief Request No. ISI-33 for the Second and Third 10-Year Inservice Inspection Intervals
| ML070871014 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/29/2007 |
| From: | Donohew J NRC/NRR/ADRO/DORL/LPLIV |
| To: | Naslund C Union Electric Co |
| Donohew J N, NRR/DORL, 415-1307 | |
| References | |
| TAC MD2033, ULNRC-05291, ULNRC-05351 | |
| Download: ML070871014 (4) | |
Text
March 29, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - CORRECTION TO AUTHORIZATION OF RELIEF REQUEST NO. ISI-33 FOR THE SECOND AND THIRD 10-YEAR INSERVICE INSPECTION INTERVALS (TAC NO. MD2033)
Dear Mr. Naslund:
In our letter to you dated March 15, 2007, the Nuclear Regulatory Commission (NRC) staff granted the relief in Relief Request No. ISI-33 for the second and third 10-year inservice inspection intervals at the Callaway Plant, Unit 1 (Callaway). The relief request was submitted in your letters dated May 18 and December 12, 2006 (ULNRC-05291 and -05351).
Inadvertently, in the safety evaluation (SE) attached to our letter dated March 15, 2007, the NRC staff issued page 2 of the SE in which the NRC staff stated the following: The difference between the 0.245-inch RMS [root mean square] error and the ASME Code-required 0.125-inch RMS error (i.e., 0.82-inch difference) will be added to the measured flaw size for the purpose of flaw evaluation. The error (in bold) is the difference in inches between the 0.245-inch and the 0.125-inch errors. This should have been stated as the 0.120-inch difference, not the 0.82-inch difference.
We are enclosing the revised Page 2 of the SE. The change is identified by a vertical bar on the right. Please replace Page 2 of the Callaway SE dated March 15, 2007, with the enclosed page.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Revised Page 2 of SE cc w/encl: See next page
March 29, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - CORRECTION TO AUTHORIZATION OF RELIEF REQUEST NO. ISI-33 FOR THE SECOND AND THIRD 10-YEAR INSERVICE INSPECTION INTERVALS (TAC NO. MD2033)
Dear Mr. Naslund:
In our letter to you dated March 15, 2007, the Nuclear Regulatory Commission (NRC) staff granted the relief in Relief Request No. ISI-33 for the second and third 10-year inservice inspection intervals at the Callaway Plant, Unit 1 (Callaway). The relief request was submitted in your letters dated May 18 and December 12, 2006 (ULNRC-05291 and -05351).
Inadvertently, in the safety evaluation (SE) attached to our letter dated March 15, 2007, the NRC staff issued page 2 of the SE in which the NRC staff stated the following: The difference between the 0.245-inch RMS [root mean square] error and the ASME Code-required 0.125-inch RMS error (i.e., 0.82-inch difference) will be added to the measured flaw size for the purpose of flaw evaluation. The error (in bold) is the difference in inches between the 0.245-inch and the 0.125-inch errors. This should have been stated as the 0.120-inch difference, not the 0.82-inch difference.
We are enclosing the revised Page 2 of the SE. The change is identified by a vertical bar on the right. Please replace Page 2 of the Callaway SE dated March 15, 2007, with the enclosed page.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483 DISTRIBUTION:
PUBLIC LPLIV Reading
Enclosure:
Revised Page 2 of SE RidsNrrDorlLpl4 DNaujock, CPNB RidsNrrPMJDonohew DCullison, EDO RIV cc w/encl: See next page RidsNrrLALFeizollahi RidsOgcRp RidsAcrsAcnwMailCenter RidsRegion4MailCenter RidsNrrDciCpnb ACCESSION NO.: ML070871014 OFFICE NRR/LPL4/PM NRR/LPL4/LA CPNB NRR/LPL4/BC NAME JDonohew LFeizollahi DNaujock DTerao DATE 3/28/07 3/28/07 3/29/07 3/29/07 OFFICIAL RECORD COPY 1
NRC Safety Evaluation dated April 7, 2004, which the letter authorizing relief request ISI-27, ADAMS Accession No. ML0410005162.
quality and safety; or (3) conformance is impractical for the facility. Pursuant to 10 CFR 50.55a(g)(4)(iv), ISI items may meet the requirements set forth in subsequent editions and addenda of the ASME Code that are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed therein, and subject to Commission approval. Portions of editions and addenda may be used provided that related requirements of the respective editions and addenda are met.
3.0 TECHNICAL EVALUATION
FOR RR NO. ISI-33 3.1 Affected Components The licensee stated that the relief request is specific to pipe weld 2-BB-01-F302.
3.2 Applicable Code As stated in the application, for the second 10-year ISI interval, the ISI code of record is the 1989 Edition with no Addenda, ASME Code,Section XI, Appendix VIII, Supplements 2 and 10, Paragraph 3.2(b) (for both supplements) which states that the RMS error for flaw depths estimated by ultrasonic testing (UT) shall not exceed 0.125 inches.
For the third 10-year ISI interval, the ISI Code of record is the 1998 Edition with 2000 Addenda, ASME Code,Section XI, Appendix VIII, Supplements 2 and 10, Paragraph 3.2(b).
3.3 Proposed Inspection The licensee proposed using the Electric Power Research Institute (EPRI) Performance Demonstration Initiative (PDI) program for the implementation of Appendix VIII, Supplement 2 in coordination with Supplement 101, Paragraph 3.2(b), 0.245-inch RMS criterion in lieu of the ASME Code-required 0.125-inch RMS criterion because of the impracticality in the licensee achieving the ASME Code-required criterion. At this time, no vendor has been able to achieve the 0.125-inch RMS criterion with the transducer applied on the pipe inside diameter (ID). The licensee would use the qualifications of Appendix VIII, Supplement 10, as administrated by the PDI, as described in its RR ISI-27, which was authorized by NRC in its letter dated April 17, 2004.
The difference between the 0.245-inch RMS error and the ASME Code-required 0.125-inch RMS error (i.e., 0.120-inch difference) will be added to the measured flaw size for the purpose l
of flaw evaluation.
3.4 Licensees Basis for Impracticality The licensees vendor performed a combined Appendix VIII, Supplements 2 and 10 (identified in the licensees submittal of May 18, 2006, as Supplement 14) performance demonstration that
June 2006 Callaway Plant, Unit 1 cc:
Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855 John ONeill, Esq.
Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street, N.W.
Washington, D.C. 20037 Mr. Keith A. Mills, Supervising Engineer Regional Regulatory Affairs/Safety Analysis AmerenUE P.O. Box 620 Fulton, MO 65251 U.S. Nuclear Regulatory Commission Resident Inspector Office 8201 NRC Road Steedman, MO 65077-1302 Mr. Les H. Kanuckel Manager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251 Missouri Public Service Commission Governor Office Building 200 Madison Street Jefferson City, MO 65102-0360 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Mr. H. Floyd Gilzow Deputy Director for Policy Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839 Mr. Dan I. Bolef, President Kay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130 Mr. Lee Fritz, Presiding Commissioner Callaway County Court House 10 East Fifth Street Fulton, MO 65151 Mr. David E. Shafer Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 66149, MC 470 St. Louis, MO 63166-6149 Manager, Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251 Mr. Keith G. Henke, Planner Division of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102 Certrec Corporation 4200 South Hulen, Suite 630 Fort Worth, TX 76109 Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116