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Category:Legal-Pre-Filed Exhibits
MONTHYEARML1025100362010-09-0808 September 2010 PIC000001-Christopher I. Grimes Resume ML1025006142010-09-0707 September 2010 NRC000001-Boric Acid Corrosion Guidebook, Revision 1 ML1025006402010-09-0707 September 2010 NRC000030-Revised Policy Statement on the Conduct of Nuclear Power Plant Operations ML1025006382010-09-0707 September 2010 NRC000025-Figures 2 Through Figure 6 ML1025006332010-09-0707 September 2010 NRC000027-The Nature of Safety Cultua Review of Theory and Research ML1024607632010-09-0303 September 2010 NSP000061-SER Section 3.0.4 ML1024607282010-09-0303 September 2010 NSP000050-Revised Prefiled Testimony of Northard/Petersen/Peterson-2009 Corrective Action Program Self-Assessment ML1024607252010-09-0303 September 2010 NSP000041-Revised Prefiled Testimony of Northard/Petersen/Peterson-Performance Recovery Plan ML1024607682010-09-0303 September 2010 NSP000069-NRC December 21, 2007 PI&R Report ML1024607712010-09-0303 September 2010 NSP000070-PINGP Pride Initiative Focus 2010 ML1024606332010-09-0303 September 2010 NSP000035B-Revised Testimony of Northard/Petersen/Peterson-Root Cause Evaluation Report 01157726 ML1024606292010-09-0303 September 2010 NSP000020-Revised Testimony of Northard/Petersen/Peterson-Petersen Resume ML1024606272010-09-0303 September 2010 NSP000035C-Revised Testimony of Northard/Petersen/Peterson-Root Cause Evaluation Report 01157726 ML1024606242010-09-0303 September 2010 NSP000019-Revised Testimony of Northard/Petersen/Peterson-Northard Resume ML1024605692010-09-0303 September 2010 Applicant Revised Exhibit NSP000001-Revised Testimony of Steven Skoyen Resume ML1024605662010-09-0303 September 2010 NSP000017-Revised Testimony of Steven Skoyen-NUREG-1765 Excerpts ML1024605152010-09-0303 September 2010 Northern States Power Co. October 2010 Evidentiary Hearing on Safety Culture Contention, Hearing Exhibits ML1024605512010-09-0303 September 2010 NSP000015-Revised Testimony of Steven Skoyen-EFR 1160372-03 ML1024605522010-09-0303 September 2010 NSP000006-Revised Testimony of Steven Skoyen-2006 AES Letter ML1024605532010-09-0303 September 2010 NSP000010-Revised Testimony of Steven Skoyen-EFR 1160372-04 ML1024605542010-09-0303 September 2010 NSP000008-Revised Testimony of Steven Skoyen-Dominion Evaluation R-4448-00-01 ML1024605552010-09-0303 September 2010 NSP000012-Revised Testimony of Steven Skoyen-EC 15651 ML1024605562010-09-0303 September 2010 2009/09/03-Applicant-Revised Exhibit NSP000003-PINGP License Renewal Application Excerpts ML1024605572010-09-0303 September 2010 NSP000013-Revised Testimony of Steven Skoyen-ACRS Letter ML1024605582010-09-0303 September 2010 NSP000007-Revised Testimony of Steven Skoyen-CAP 1160372 ML1024605592010-09-0303 September 2010 NSP000011-Revised Testimony of Steven Skoyen-EC 15044 ML1024605602010-09-0303 September 2010 NSP000016-Revised Testimony of Steven Skoyen-ACRS July 2009 Meeting Transcript Excerpts ML1024605622010-09-0303 September 2010 Applicant Revised Exhibit NSP000004-Root Cause Evaluation Report 01160372-01 ML1024605632010-09-0303 September 2010 NSP000018-Revised Testimony of Steven Skoyen-CE 01140617-03 ML1024605642010-09-0303 September 2010 NSP000009-Revised Testimony of Steven Skoyen-CE 1233806-2 ML1024605652010-09-0303 September 2010 Applicant Revised Exhibit NSP000002-Schematic Representation of PINGP Containment ML1022504662010-08-13013 August 2010 NRC Staff Exhibit 63 - Boric Acid Corrosion Guidebook, Revision 1: Managing Boric Acid Corrosion Issues at PWR Power Stations EPRI, Palo Alto, CA (2001) 1000975 Pages 4-25 & 4-26 ML1022504702010-08-13013 August 2010 2010/08/13-NRC Staff Exhibit 4A - NUREG-1800 Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) (September 2005), (Excerpt) ML1022504772010-08-13013 August 2010 NRC Staff Exhibit List ML1022504962010-08-13013 August 2010 Northard Exhibit 43, Section 3.0.4. of NRC SER ML1022504982010-08-13013 August 2010 Northard Exhibit 48, WM-0491 - Prairie Island Corrective Backlog ML1022505002010-08-13013 August 2010 Skoyen Exhibit 17, NUREG-1765 Excerpt ML1022505082010-08-13013 August 2010 Northard Exhibit 52, Pride Initiative Focus/2010 ML1022505132010-08-13013 August 2010 Skoyen Exhibit 18, CE01140617-03 Potential IWE Non-Compliance ML1022505142010-08-13013 August 2010 Northard Exhibit 42, Event Cross References in 2009 ML1022504952010-08-10010 August 2010 Skoyen Rebuttal Exhibits List ML1022505012010-08-10010 August 2010 List of Northard Rebuttal Exhibits ML1024607592010-08-0606 August 2010 NSP000066-PINGP Corrective Backlog 2010 ML1022504752010-08-0404 August 2010 NRC Staff Exhibit 62 - Summary of July 28, 2010 Public Meeting to Discuss Observations and Lessons Learned During the Pilot Application of the Nuclear Energy Institutes Nuclear Safety Culture Assessment Process (August 4, 2010) ML1021607812010-08-0404 August 2010 Intervenor-Exhibit 21-Xcel Management Review Committee Meeting Summary No. 2010-01, Msrc Meeting Date March 17 and 18, 2010 (NSPM Prod 00000267) ML1021607642010-08-0404 August 2010 Intervenor-Exhibit 1-Resume for Christopher I. Grimes ML1025006752010-08-0404 August 2010 NRC000058-Summary of July 28, 2010 Public Meeting to Discuss Observations and Lessons Learned During the Pilot Application of the Nuclear Energy Institute'S Nuclear Safety Culture Assessment Process (August 4, 2010) ML1021503902010-07-30030 July 2010 Applicant-Northard Exhibit 4-INPO V NRC Nuclear Safety Culture Components ML1021503922010-07-30030 July 2010 Applicant-Northard Exhibit 5 - Nuclear 2010 Business Plan Overview ML1021503932010-07-30030 July 2010 Applicant-Northard Exhibit 10-FP-PA-HU-03, Rev. 6, Human Performance Observation Program. 2010-09-08
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NSP000018 SKOYEN EXHIBIT 18 CE01140617-03 Potential IWE Non-compliance Event Description This CE evaluates failure to report refuel cavity leakage and the associated potential for degradation of the containment vessel as required for the IWE program.
The Code of Federal Regulations 10CFR50.55a requires in paragraph (b)(2)(ix)(A) that the licensee shall evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas. For each inaccessible area identified, the licensee shall provide the following in the ISI Summary Report as required by IWA-6000: A description of the type and estimated extent of degradation, and the conditions that led to the degradation; An evaluation of each area, and the result of the evaluation, and; A description of necessary corrective actions.
Refuel cavity leakage that contacts the containment vessel is considered conditions in accessible areas that could indicated the presence of or result in degradation of inaccessible areas. Accordingly, the site should have included a discussion of the leakage in the 90 day summary report following each outage that such leakage occurred. The site failed to report the 2R24 refuel cavity leakage and previously in 2R22.
The primary purpose of this CE is to identify instances of leakage since the beginning of the current IWE interval (September of 1996) that were not appropriately reported.
Following is a summary of refuel cavity leakage events and report status based on a review of associated CAPs, 90 day summary reports, and other sources such as program notes. The following is based on a reasonable search of available documentation and may not be complete or conclusive.
Outage Approx. Leakage Cap # Included in 90 Day Date Report?
2R18 Apr-97 Unknown 1R19 Oct-97 Unknown 2R19 Oct-98 Leakage in Sump B and other 00051045 Yes. Reported by locations. Initial AES amendment evaluation. AR00122811 1R20 Apr-99 Leakage in Sump B and other 00057041 Yes. Reported by locations. amendment AR00122811 2R20 Apr-00 Unknown 1R21 Jan-01 No Leakage. Installed N/R Strippable liner.
2R21 Feb-02 No Leakage. Installed N/R Strippable liner.
1R22 Nov-02 Leakage in Sump B. 00284714 Yes. Included in Strippable liner failed to stop original summary leakage. report.
2R22 Sep-03 Leakage in various locations. 00531162 Failed to include in report.
1R23 Sep-04 Leakage noted in regen room 00751496 N/R
2R23 May-05 No Leakage. Caulked N/R penetrations 1R24 May-06 No Leakage. Caulked N/R penetrations 2R24 Nov-06 Leakage in Sump B. Revised 01064513 Failed to include in AES evaluation. report.
1R25 Jan-08 No Leakage. Caulked N/R penetrations Indications are the site failed to report leakage for 2R22 and 2R24. Other outages either did not have leakage or the status of leakage and the need to report is unknown.
Corrective Actions and Final Disposition A corrective action AR 01140617-05 has been initiated to submit an amendment to the 2R22 and 2R24 90 day summary reports to meet the requirements of 10CFR50.55a(b)(2)(ix)(A). Submission of the amendment will restore compliance and allow the associated OBN to be closed.