LIC-12-0004, Delay 2012 Refueling Outage and Extend In-service Inspection (ISI) and In-service Test (IST) Intervals
| ML12018A041 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/17/2012 |
| From: | Herman J Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-12-0004, TAC ME4541 | |
| Download: ML12018A041 (2) | |
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Omaha Public Power District 444 South 16th Street Mall Omaha, NE 68102-2247 January 17,2012 LlC-12-0004 U. S. Nuclear Regulatory Commission Attn : Document Control' Desk Washington, D.C. 20555
References:
- 1.
Docket No. 50-285
- 2.
Letter from NRC (M. T. Markley) to OPPD (D. J. Bannister), "Fort Calhoun Station, Unit No.1 - Request For Relief RR-12 From ASM E Code Case N-722 Visual Examination of the Reactor Vessel Hot l eg Nozzle To Safe End Dissimilar Metal Welds (TAC No. ME4541 )," dated August 18, 2011 (NRC-11-0090) (ML112270290)
- 3. Letter from NRC (E. E. Collins) to OPPD (D. J. Bannister),
"Confirmatory Action Letter - Fort Calhoun Station," dated September 2,2011 (NRC-11-0109) (ML112490164)
SUBJECT:
Delay 2012 Refueling Outage and Extend In-service Inspection (1St) and In-service Test (1ST) Intervals Fort Calhoun Station (FCS) remains in the 2011 refueling outage (RFO), which began April 9, 201 11. Completion of the 2011 RFO has been delayed by the onset of Missouri River flooding that impacted the site in June 2011, causing FCS to be out of service for a period exceeding six months. The 2011 RFO continues while the Omaha Public Power District (OPPD) addresses commitments (Reference 3) from the FCS Post-Flood Recovery Plan.
The purpose of this letter is to notify the NRC that the next RFO at FCS will not occur in 2012 as originally planned but is now expected to occur in the spring or fall of 2013 depending upon when FCS resumes power operations. Because of this delay, OPPD is extending lSI and 1ST intervals as well as the containment concrete/tendon inspection frequency.
The code of record for Fort Calhoun Station's fourth lSI interval is American Society of Mechanical Engineers (ASME),Section XI, 1998 Edition with 2000 Addendum. Paragraph IWA-2430(e) allows the inspection interval to be extended for a period equivalent to the length of the outage. The code of record for Fort Calhoun Station's fourth 1ST Interval is ASME, OM Code, 1998 Edition with 2000 Addenda.
Section ISTA-3130(e) allows the inspection interval to be extended for a period equivalent to the length of the outage.
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U. S. Nuclear Regulatory Commission LlC-12-0004 Page 2 Therefore, the fourth lSI and 1ST intervals will be extended from their current end on September 25,2013, for a period equivalent to the length of the 2011 RFO.
The code of record for the second interval of the containment lSI is ASME,Section XI, 2001 Edition with 2003 Addenda (Subsections IWE and IWL). Paragraph IWA-2430(e) allows the inspection interval to be extended for a period equivalent to the length of the outage. Therefore, the containment lSI interval will be extended from its current end on September 8, 2018, for a period equivalent to the length of the 2011 RFO.
In addition, paragraphs IWL-2410(c) and IWL-2420(c) allow the examination of concrete and tendons required every 5 years to be extended by up to one year. Therefore, the containment concrete and tendon inspections are planned for completion by the end of the fourth quarter of 2012.
Please note that Relief Request RR-12 (Reference 2) implies that there will be a refueling outage in 2012, which as stated above is now expected to occur in either the spring or fall of 2013. OPPD intends to submit another relief request for the visual examination required by ASME Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities." A recent analysis by Westinghouse supports additional relief on the reactor vessel hot leg nozzle-to-safe end welds.
When power operations resume, OPPD will notify the NRC as to the start of the next RFO and the specific dates when the aforementioned I'SI and 1ST intervals end (AR 50856). No other commitments to the NRC are contained in this submittal.
If you have any questions regarding this submittal, please contact Mr. Bill Hansher at (402) 533-6894.
Sincerely, ivision Manager-Nuclear Engineering JBH/GLM/mle c:
E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector