Letter Sequence Other |
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MONTHYEARML0800901542008-01-22022 January 2008
Summary of Conference Call Held with PWR Licensees on the Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
Project stage: Other
ML0804503232008-03-0303 March 2008
Summary of Third Conference Call Held with Pressurized-Water Reactor Licensees on Status of NRC Review of License Amendment Requests for Steam Generator Tube Inspections
Project stage: Approval
ML0802500852008-03-26026 March 2008
Summary of Second Conference Call Held on January 16, 2008, with PWR Licensees on New Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
Project stage: Other
2008-03-26
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Category:Memoranda
MONTHYEARML23179A2132023-07-0505 July 2023
Approval for Credit for the Wolf Creek Generating Station Operational Safety Review Team to the Baseline Inspection Samples/Hours
ML22165A0882022-06-14014 June 2022
Information Request, Security IR 2022403
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21309A5482021-11-15015 November 2021
NSIR Staff Review of the Wolf Creek Generating Stations Security Plan Training & Qualification Plan & Safeguards Contingency Plan for the Verification of ASM EA 20 091 Incorporation
ML21243A4492021-09-0202 September 2021
ISFSI Technical Assistance Request - Review of Physical Security Plan
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML18173A0082018-06-20020 June 2018
Cancelling Numerous Inspection Report Numbers
ML17019A2912017-01-19019 January 2017
Notice of Closed Regulatory Conference with Wolf Creek Generating Station
ML17019A2932017-01-19019 January 2017
Notice of Closed Regulatory Conference with Wolf Creek Generating Station
ML16064A1872016-03-0404 March 2016
Closed Pre-Decisional Enforcement Conference with Wolf Creek Nuclear Operating Corporation
ML15251A0092015-09-11011 September 2015
Review of Revision 28 to the Updated Safety Analysis Report
ML15015A1712015-01-0808 January 2015
Focused Baseline Inspection at the Wolf Creek Site for a Major Essential Service Water Modification
ML14197A3442014-07-25025 July 2014
Review of Revision 27 to the Updated Safety Analysis Report
ML13204A2432013-07-24024 July 2013
Notice of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13109A2342013-07-12012 July 2013
Safety Evaluation Regarding Wolf Creek Generating Station - Loss of Offsite Power and Augmented Inspection, Issue for Resolution 2012-004
ML13179A1012013-07-0909 July 2013
7/30/13 Notice of Forthcoming Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station
ML13093A0592013-04-0202 April 2013
Public Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Performance Assessment Results for Wolf Creek Generating Station for 2012
ML13078A1552013-03-20020 March 2013
License Amendment Request to Change Diesel Generator Surveillance Requirements
ML12249A0292012-09-0606 September 2012
9/20/12 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Wolf Creek Station
ML1222602142012-08-16016 August 2012
Iolb Evaluation of Ifr 2012-04 Relating to Wolf Creek Loss of Offsite Power and Notification of Unusual Event
ML12011A1012012-01-19019 January 2012
Summary of Meeting with NEI and to Address Di&C Issues
ML1101106702011-02-0707 February 2011
Fire Protection Safety Evaluation Input for Wolf Creek Generating Station Regarding License Amendment Request for Deviation from the Fire Protection Program Requirements
ML1006010322010-03-0101 March 2010
Cy 2009 Baseline Inspection Completion
ML0929300152009-10-20020 October 2009
Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02
ML0928003162009-10-16016 October 2009
Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively
ML0925404602009-09-10010 September 2009
Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ
ML0920306202009-07-31031 July 2009
Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station
ML0917002962009-07-30030 July 2009
Issuance of Amendment 183, Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to Extend the Surveillance Frequency on ESFAS Slave Relays from 92 Days to 18 Months
ML0835705252008-12-24024 December 2008
Meeting Notice, Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Pre-Application of Post-fire Safe Shutdown Issues at Wolf Creek
ML0829405182008-11-10010 November 2008
Renewal of Full-Power Operating License for the Wolf Creek Generating Station, Unit 1
ML0813006882008-05-0909 May 2008
03/05/2008 Meeting Minutes of Subcommittee on Plant License Renewal Regarding Wolf Creek Generating Station
ML0812001002008-04-29029 April 2008
End of Cycle Meeting with Wolf Creek Nuclear Operation Corporation
IR 05000482/20080072008-04-24024 April 2008
IR 05000482-08-007, on 01/15/2008 - 03/13/2008, Wolf Creek Generating Station, NRC Special Inspection
ML0810805452008-04-18018 April 2008
05/01/2008-Notice of Forthcoming Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Safety Evaluation Report Open Items Related to Metal Fatigue Analyses for License Renewal
ML0807904692008-04-10010 April 2008
Summary of Teleconference with Wolf Creek Nuclear Operating Corporation, Ameren Union Electric Company for Callaway Plant, and Performance Contracting, Inc. Containment Sump Head Loss Testing
ML0802500852008-03-26026 March 2008
Summary of Second Conference Call Held on January 16, 2008, with PWR Licensees on New Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
ML0807404192008-03-14014 March 2008
Assessment of Inspections of Dissimilar Metal Butt Welds in a Retired Pressurizer
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0807304562008-03-13013 March 2008
Cy 2007 Baseline Inspection Completion
ML0804503232008-03-0303 March 2008
Summary of Third Conference Call Held with Pressurized-Water Reactor Licensees on Status of NRC Review of License Amendment Requests for Steam Generator Tube Inspections
ML0807300242008-02-22022 February 2008
Status Report and Proposed Agenda for the ACRS Subcommittee on March 5, 2008 Related to the License Renewal Application of Wolf Creek Generating Stations Unit 1
ML0804504682008-02-19019 February 2008
Federal Register Notice Regarding the Meeting of the ACRS Subcommittee on Wolf Creek Plant License Renewal Application, March 5, 2008
ML0803603712008-02-0707 February 2008
Advisory Sub-Committee on Reactor Safeguards Review of the Wolf Creek Generating Station, License Renewal Application - Safety Evaluation Report with Open Items
ML0800901542008-01-22022 January 2008
Summary of Conference Call Held with PWR Licensees on the Temporary License Amendment Needed for Steam Generator Tube Inspections in Spring 2008 Refueling Outages
ML0733103642007-11-27027 November 2007
Revised Notice of Meeting with Wolf Creek Nuclear Operating Corp, to Discuss NRC Staff'S Request for Information on Licensee'S Supplemental Letter Dated September 27, 2007, to the Application Dated February 21, 2006, to Revise TS 5.5.9
ML0733101982007-11-27027 November 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation, to Discuss NRC Staff'S Request for Additional Information on Licensee'S Proposed Main Steam and Feedwater Isolation System Modification in Its Application Dated March 14, 2007
ML0732500032007-11-21021 November 2007
Memo to Thomas G. Hiltz Key Issues for Discussion for November 28, 2007 Meeting on Steam Generator Tube Inspection License Amendment (Tac MD0197)
ML0730901272007-11-0808 November 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss NRC Staff'S Request for Additional Information on Licensee'S Supplemental Letter to Letter Dated September 27, 2007, to Application Dated February 21, 2006
ML0727000542007-10-0202 October 2007
Summary of Telephone Conference Call Held on 9/26/07, Between the U.S. NRC and Wolf Creek Nuclear Operating Corporation, Concerning Draft Requests for Additional Information Pertaining to the Wolf Creek Generating Station, Unit 1, LRA
2023-07-05
[Table view] |
Text
January 22, 2008 MEMORANDUM TO: Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Jack N. Donohew, Senior Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
WOLF CREEK GENERATING STATION -
SUMMARY
OF CONFERENCE CALL HELD WITH PWR LICENSEES ON THE NEW TEMPORARY LICENSE AMENDMENT NEEDED FOR STEAM GENERATOR TUBE INSPECTIONS IN SPRING 2008 REFUELING OUTAGES (TAC NO. MD7762)
The NRC staff has been reviewing the license amendment request (LAR), for the Wolf Creek Generating Station (WCGS), submitted by letter dated February 21, 2006 (ET 06-0004)
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML060600456). In this review, Wolf Creek Nuclear Operating Corporation, the licensee for Wolf Creek Generating Station, (the licensee) has submitted two supplemental letters providing responses to NRC questions and we have conducted three meetings with the licensee, including the closed meeting held at the Westinghouse office on December 13, 2007.
Following the December 13, 2007, meeting with the licensee, the SG [Steam Generator] Tube Integrity and Chemical Engineering Branch (CSGB), which is reviewing the WCGS application, stated that it was not prepared to approve the Westinghouse methodology that is being used by the licensee to justify its LAR. Therefore, pressurized-water reactor (PWR) licensees, like the licensee, will need to consider submitting LARs to cover SG inspections in the upcoming spring 2008 refueling outages if they want to limit the inspection and repair of steam generator (SG) tubes in the upcoming spring 2008 refueling outages. Without such LARs, the plant Technical Specifications (TSs) require the inspection of the entire tube in the tubesheet and repair by the repair criteria stated in the TSs. Licensees have previously had one-cycle amendments approved that did not require inspections of the portion of the SG tubes more than 17 inches below the top of the tubesheet. These new temporary LARs could not be the same one-cycle LARs that have been approved for PWR licensees in the past few years because they could not rely on the justification that submitted and approved by the NRC staff in these amendments.
A call was held with the licensee on December 21, 2007, since it had submitted the LAR that was under review by the NRC staff. A further call was held on January 3, 2008, that was a followup to the December 21, 2007, call with only the licensee and included other PWR licensees that may be affected by the NRC staff decision to have this temporary LAR for the spring 2008 outages because these licensees may submit new LARs to limit the inspection and repair of the tubes more than 17 inches below the top of the tubesheet.
T. Hiltz This memorandum is to document the January 3, 2008, call, the licensee attendees on the call (Enclosure 1), and the questions addressed in the call (Enclosure 2). In the discussion on the three questions in Enclosure 2, the NRC staff stated the following:
- 1. If the tubes are not proposed to be removed from service, the licensee must provide a technical basis for the proposed plugging limit on circumferential extent of flaws located 17 inches or more from the top of the tubesheet. This limit must include allowances for flaw growth in the operating cycle and eddy current measurement error in inspecting the tubes.
- 2. In view of the unresolved issues pertaining to the B* distance down the tubesheet, CSGB is unable to conclude at this time that the ratio of steam line break leakage to normal operating leakage is less than 2 (the Bellwether factor) for flaws at any location within the thickness of the tubesheet. For this reason, the licensees should propose a conservative estimate of this leak rate ratio, including its technical basis, for flaws which may be located 17 inches or more below the top of the tubesheet. (Note, this ratio should be reflected in the special technical specification reporting requirement in lieu of the current value of 2.)
- 3. A key premise of the new interim technical position is that the welds are capable of transmitting the axial load in the tubes to the tubesheet. For this reason, the licensees should provide a discussion of their inspection and repair strategy with respect to the tube-to-tubesheet welds that will be implemented for the next SG tube inspection. (Note, the staff is interested only in whether the welds will be addressed in a consistent manner with the lower 4-inches of tubing (below 17 inches in the tubesheet) rather than the specific sampling strategy or inspection methods to be employed.)
- 4. Extensive documentation is not expected to be required to be submitted; however, three items are needed. These are the following: (1) justification for proposed alternate repair criteria, eddy current error, and crack growth through the operating cycle; (2) quantified rationale for bellwether ratio considered appropriate; and (3) discussion on how welds in the tubesheet are inspected and repaired. If this documentation is in previous submittals to the NRC, the licensee may reference those submittals in its application.
The NRC staff stated that axial cracks in the bottom 4 inches of the tube in the tubesheet should be acceptable. The licensees asked what time would be needed by NRC to address the LARs submitted for the spring 2008 outages. The NRC staff did not have an answer, but stated that PWR licensees should come up with a plan on how they submit these LARs and inform the staff. This ended the discussion on the three questions. It may be necessary for further discussion and future calls between the staff and the licensees.
Docket No. 50-482
Enclosures:
- 1. List of Attendees
- 2. List of Questions addressed
ML080090154 NRC-001 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/CSGB/BC NRR/LPL4/BC NAME JDonohew JBurkhardt AHiser THiltz DATE 1/22/08 1/9/08 1/16/08 1/22/08 LIST OF ATTENDEES PARTICIPATING IN CONFERENCE CALL OF JANUARY 3, 2008 WITH WOLF CREEK NUCLEAR OPERATING CORPORATION AND OTHER PRESSURIZED WATER REACTOR (PWR) LICENSEES NAME AFFILIATION NRC: J. Donohew NRC/NRR/DORL E. Murphy NRC/NRR/DCI S. Lingam NRC/NRR/DORL A. Johnson NRC/NRR/DCI M. Thorpe-Kavanaugh NRC/NRR/DORL Licensees: S. Wideman WCNOC P. Wagner WCNOC L. Ratzlaff WCNOC G. Boyers FPL E. Korkowski FPL D. Gerber Dominion J. Smith Exelon M. Sears Exelon D. Chrzanowski Exelon S. Leshnoff Exelon R. Hall Exelon R. Gesior Exelon A. Shahkarami Exelon G. Smith Exelon W. Moore Southern Co R. Mullins Southern Co R. Kidwell Luminant B. Mays Luminant P. Fabian Salem D. Mayes Duke Energy J. Kendrickson Robinson J. Stringfellow Southern Nuclear R. Grahm Southern Nuclear P. Conley Southern Nuclear L. Hill Southern Nuclear S. LeBlanc Southern Nuclear Public: H. Lagally Westinghouse G. Whiteman Westinghouse C. Cassino Westinghouse J. Kendra Westinghouse M. Melton NEI H. Cothron EPRI Where: DCI = Division of Component Integrity DORL = Division of Operating Reactor Licensing EPRI = Electric Power Research Institute FPL = Florida Power and Light NEI = Nuclear Energy Institute NRC = Nuclear Regulatory Commission NRR = Office of Nuclear Reactor Regulation WCNOC = Wolf Creek Nuclear Operating Corporation ENCLOSURE 1
THE THREE QUESTIONS ADDRESSED IN THE CONFERENCE CALL OF JANUARY 3, 2008 The three questions/issues that E. Murphy was going to follow up on following the call on December 21, 2007, with WCNOC:
- 1. Is the weld excluded from inspection and can significant circumferential cracks in the weld be ignored?
- 2. How much of the Bellwether approach can be used to evaluate Steam Line Break leakage?
- 3. Level of documentation required to support interim Alternate Repair Criteria for the steam generator tubes inspected?
ENCLOSURE 2
