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MONTHYEARML0226807122002-09-25025 September 2002 Review of Steam Generator Inspection Results During 1R17 Project stage: Approval ML0234005302002-12-0606 December 2002 12/6/2002, ANO-1, Unit 1, Summary of Conference Calls on Steam Generator (SG) Inspection Results During 1R17 Project stage: Other ML0234303282002-12-0606 December 2002 12/6/2002, ANO-1, Unit 1, Enclosure 2, Summary of Conference Calls on Steam Generator (SG) Inspection Results During 1R17 Project stage: Other 2002-12-06
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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
[Table view] Category:Meeting Summary
MONTHYEARML23257A2412023-09-19019 September 2023 Summary of August 15, 2023, Pre-submittal Teleconference with Entergy Operations, Inc. to Discuss Proposed License Amendment Request Concerning Pressurizer Heaters for Arkansas Nuclear One, Unit 1 ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22215A1912022-08-0909 August 2022 Summary of July 13, 2022, Teleconference Meeting with Entergy Operations, Inc. to Discuss Planned License Amendment Requests to Adopt Technical Specifications Task Force (TSTF) Traveler 505, Risk-Informed Extended Completion Times ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22151A1302022-06-0202 June 2022 May 10, 2022, Summary of Teleconference Meeting W/Entergy Operations, Inc. to Discuss a Planned Alternative for a One-Time Schedule Extension for the In-Service Examination of Control Rod Drive Mechanism Penetration No. 1 in the Reactor Ves ML22125A2452022-05-0909 May 2022 May 3, 2022, Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for ANO, Units 1 & 2 Regarding Proposed Revision to Emergency Plan and On-Shift Staff Analysis ML22003A0562022-01-10010 January 2022 Summary of December 16, 2021, Presubmittal Teleconference with Entergy Operations, Inc. to Discuss Proposed Amendment Request Concerning TS 3.4.4, RCS Loops, Modes 1 and 2, for Arkansas Nuclear One, Unit 1 ML21323A0472021-12-0606 December 2021 Summary of Public Meeting on November 5, 2021, with the National Organization of Test, Research, and Training Reactors on Operator Licensing for Research and Test Reactors ML21288A0392021-10-18018 October 2021 September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21117A0262021-05-0505 May 2021 Summary of Teleconference with Entergy Operations, Inc. to Discuss Forthcoming LAR Concerning Reactor Coolant System Primary Activity and Primary-to-Secondary Leak Rate ML20337A1572020-12-0808 December 2020 Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss the Forthcoming Supplemental Response Concerning Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 ML20287A4012020-10-26026 October 2020 Summary of September 17, 2020, Meeting with Entergy to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Request to the Extend Allowable Outage Time for the Emergency Cooling Pond ML20260G9992020-09-16016 September 2020 Summary of August 4, 2020, Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Regarding Adoption of 10 CFR 50.69 ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML20153A2252020-06-0404 June 2020 April 29, 2020, Summary of Meeting with Entergy Operations, Inc. to Discuss a Proposed Relief Request Use of Carbon Fiber Reinforced Polymer Piping for Underground Service Water Piping at Arkansas Nuclear One, Units 1 and 2 ML19182A0332019-07-10010 July 2019 Summary of Teleconference with Entergy Operations, Inc. Regarding Proposed License Amendment Request Revised Fuel Handling Analysis and Adoption of Various TSTF Travelers for Arkansas Nuclear One, Unit 2 ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML17353A1542017-12-22022 December 2017 Summary of Public Meeting with Entergy Operations, Inc., on Proposed Changes to Emergency Plans to Revise Emergency Action Levels for Arkansas; Grand Gulf; River Bend; and Waterford (EPID-L-2017-LRM-0060) ML16109A3642016-04-18018 April 2016 Summary of Meeting to Discuss Supplemental Inspection Results and Annual Assessment Meeting with Entergy Operations Inc. Regarding 2015 Performance of Arkansas Nuclear One ML15348A1882016-01-0606 January 2016 Summary of October 28, 2015, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc. to Discuss Flood Analysis Associated with Arkansas Nuclear One, ML15267A4182015-09-24024 September 2015 Summary of Meeting to Discuss Arkansas Nuclear One Performance Improvement ML15225A2542015-08-14014 August 2015 Summary of 4/20-23/2015 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML15007A4782015-01-15015 January 2015 Summary of July 15-18, 2013, Arkansas Nuclear One, Unit 2, Audit Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 ML14356A1722014-12-22022 December 2014 Summary of Site Audit to Support the Review of a License Amendment Request for Arkansas Nuclear One, Unit 2 to Transition to the National Fire Protection Association (NFPA) Standard 805 Fire Protection Licensing Basis ML14197A5832014-09-18018 September 2014 Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1 ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14213A4272014-09-12012 September 2014 Summary of July 16, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers Nuclear Regulatory Commission, and Entergy Operations Inc. to Discuss Flooding Analysis Associated with Arkansas Nuclear One, Units 1 and 2 ML14162A3712014-06-26026 June 2014 5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1 ML14170A0602014-06-23023 June 2014 Summary of 5/27/2014 Conference Call Regarding Refueling Outage Steam Generator Inspection ML14163A0502014-06-13013 June 2014 Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections ML14128A5122014-05-0909 May 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Unit 1 Dropped Stator ML13172A0292013-07-0909 July 2013 Summary of 5/10/2013 Conference Call with Entergy Operations, Inc., 2013 Steam Generator Tube Inspections at Arkansas Nuclear One, Unit 1 ML13142A2272013-05-22022 May 2013 Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One ML13043A6112013-02-26026 February 2013 Summary of 1/25/2013 Conference Call Regarding the Upcoming 2013 Steam Generator Tube Inspections ML12276A3012012-10-12012 October 2012 Summary of October 25, November 8, and November 10, 2011, Conference Calls Related to Fall 2011 Refueling Outage Steam Generator Tube Inspections ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12240A4162012-08-27027 August 2012 Public Meeting with Entergy Operations, Inc to Discuss the Performance of the Subject Facilities and Current Regulatory Issues ML12222A0312012-08-0808 August 2012 Arkansas Monitoring Call Summary ML12171A3662012-07-16016 July 2012 6/12-13/2012 Summary of Meeting at the Plant Site in Russellville, AR, to Discuss Entergy Operations, Inc.'S License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2 ML1202704162012-02-13013 February 2012 1/26/2012 - Summary of Meeting with Entergy and Exelon to Discuss Recent Once-Through Steam Generator Inservice Inspection Results ML1127903812011-11-0101 November 2011 Summary of Meeting with Entergy Operations, Inc. to Discuss Amendment Request to Revise Arkansas Nuclear One, Unit 2's Fuel Handling Accident (FHA) Analysis and Several TSTFs 51, 272, 286, and 471 That Support FHA ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc 2023-09-19
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Text
December 6, 2002 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 1 (ANO-1) -
SUMMARY
OF CONFERENCE CALLS ON STEAM GENERATOR (SG) INSPECTION RESULTS DURING 1R17 (TAC NO. MB6339)
Dear Mr. Anderson:
On October 1, 3, 17, and 23, 2002, the Nuclear Regulatory Commission (NRC) staff participated in conference calls with Entergy Operations, Inc. (Entergy) representatives regarding the ongoing SG tube inspection activities at ANO-1. A summary of the conference calls is provided in Enclosure 1. The materials that Entergy provided in support of these calls is provided in Enclosure 2.
The NRC appreciates the resources you provided to support these conference calls.
TAC MB6339 is considered closed.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosures:
As stated cc w/encls: See next page
December 6, 2002 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT NO. 1 (ANO-1) -
SUMMARY
OF CONFERENCE CALLS ON STEAM GENERATOR (SG) INSPECTION RESULTS DURING 1R17 (TAC NO. MB6339)
Dear Mr. Anderson:
On October 1, 3, 17, and 23, 2002, the Nuclear Regulatory Commission (NRC) staff participated in conference calls with Entergy Operations, Inc. (Entergy) representatives regarding the ongoing SG tube inspection activities at ANO-1. A summary of the conference calls is provided in Enclosure 1. The materials that Entergy provided in support of these calls is provided in Enclosure 2.
The NRC appreciates the resources you provided to support these conference calls.
TAC MB6339 is considered closed.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosures:
As stated cc w/encls: See next page DISTRIBUTION:
PUBLIC ZFu PDIV-1 Reading KKarwoski RidsOgcRp CMarshall, RIV RidsAcrsAcnwMail Center AHowell, RIV RidsNrrDlpmLpdiv1 (RGramm) RidsNrrPMTAlexion Package No: ML023430538 No.: ML023430328 Accession No.: ML023400530 *no substantive change from summary input OFFICE PDIV-1/PM PDIV-1/LA EMCB/SC PDIV-1/SC NAME TAlexion DJohnson LLund* RGramm DATE 12/04/2002 12/03/2002 11/21/02 12/04/2002 OFFICIAL RECORD COPY
SUMMARY
OF CONFERENCE CALLS WITH ENTERGY OPERATIONS, INC. (ENTERGY/LICENSEE)
REGARDING 2002 STEAM GENERATOR (SG) INSPECTION RESULTS ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1)
The Nuclear Regulatory Commission (NRC) staff participated in conference calls with Entergy representatives on October 1, October 3, October 17, and October 23, 2002, to discuss the SG inspection results from the 17th refueling outage at ANO-1. The calls are summarized below.
Inspection/Plugging Plans to Address the Industry Identified Severed Tube Issue During the calls prior to and on October 17, 2002, the NRC and the licensee discussed the licensees actions in response to NRC Information Notice 2002-02 (IN 2002-02), Recent Experience with Plugged Steam Generator Tubes (Agencywide Documents Access and Management System Accession Number ML013480327). As discussed in the information notice, certain plugged tubes may be susceptible to severance as a result of tube vibration and other factors (e.g., tube swelling).
The licensee has identified twelve susceptible plugged tubes needing corrective action. These tubes have explosive plugs and will not be deplugged and/or stabilized. Instead, the licensee will cage all the susceptible tubes which is consistent with the Babcock & Wilcox Owners Group (BWOG) short term recommendations. The recommendations call for stabilizing and plugging all the tubes surrounding the susceptible tube. Among the adjacent tubes surrounding the susceptible tubes in the ANO-1 SGs, some had already been sleeved or stabilized previously. As a result, the licensee plans to plug and stabilize the rest of the neighboring tubes; a total of 61. The licensee believes that the sleeved tubes (plugged or unplugged) adjacent to susceptible tubes do not need further remedial action (i.e., plugging and stabilization) since the sleeve will act both as a stabilizer and as a pressure boundary. In addition, the licensee stated that plans are under way to replace its SGs during the outage in 2005.
No indications that a tube had severed were identified during this inspection (e.g., no wear scars were found in the tubes adjacent to the 12 susceptible plugged tubes).
Inspection Scope On October 17, 2002, the NRC and the licensee discussed the SG tube inspection scope, the eddy current data analysis results, tube plugging and repair plans, and in-situ pressure testing.
At the time of the call, the licensee had already completed the inspection except some plus-point probe data analysis. Details of the inspection scope and results are contained in the attached inspection summary Entergy provided in support of this call. Additional clarifying information provided during the call is provided below.
The inspection scope included the following:
C 100% of tubes in both SGs by bobbin probes.
C 100% of tubes in the sludge pile region with plus-point probes.
C 100% of all dents over 2 volts above Tube Support Plate (TSP) 8 with plus-point probes.
Enclosure 1
Inspection Results Prior to shutdown for the inspection, there were only trace indications of primary-to-secondary leakage. Therefore, no secondary side pressure tests were conducted during the outage.
The licensee indicated that the location and size of indications detected during the outage inspection will be included in the 90-day report issued after the outage. During the phone call, the licensee discussed significant indications found as a result of the inspections.
The licensee detected outside diameter inter-granular attack (OD IGA) flaws in the upper tubesheet. They detected 329 indications in SG A, and 231 in SG B. None of the indications exceed the criteria for plugging. The alternate repair criteria will continue to be applied. The licensee was in a process of evaluating the growth rate at the time of the call but indicated that the indications observed were similar to what had been observed previously.
The licensee also detected 1383 tubes in SG A and 778 tubes in SG B with axial indications at the end of the tube extending outside the tubesheet. The overall number is very similar to the previous inspection. None of the indications extended into the portion of tube in contact with the carbon steel tubesheet (i.e., none had to be repaired by re-rolling).
The licensee also detected TSP wear degradation in both SGs. There were 437 wear indications in SG A and 448 in SG B. The licensee stated that the deepest indication is only 25% through-wall.
The licensee detected 39 axial indications in the upper roll transition region in each of the SGs, and indicated that most of the indications will likely be repaired by re-rolling.
The licensee detected indications in tubes which had been re-rolled. Some of these indications were located inside the pressure boundary but most of them were outside. They found 1469 re-roll crack indications outside the pressure boundary in SG A, and 1077 in SG B. (They detected 1245 in SG A and 951 in SG B in the previous inspection.) The licensee detected 29 re-roll crack indications inside the pressure boundary in SG A and 16 in SG B. The number of tubes with indications this outage is less than the number observed in the previous outage. Of the 45 tubes with indications, 11 were attributed to axial cracks while some were OD volumetric indications such as IGA. The licensee was still determining if any of the indications were circumferential.
An indication was detected in the sludge pile region on the lower tubesheet in SG B. The indication was detected with a bobbin probe and a rotating probe. The licensee stated that it is less than 0.2 inches in axial and circumferential extent and is a shallow OD IGA flaw.
A total of 32 freespan flaws were detected in SG A and 5 in SG B. Most of them were classified as groove IGA. The licensee also detected 2 volumetric indications in the portion of tubes within the tube support plate. One of these indications appeared to initiate from the inside diameter based on bobbin and plus-point probes. This indication has been there for many years and has not changed. The other indication is a single OD-initiated volumetric indication at the lower edge of the 6th TSP. No indications were found at dents, in sleeves, or on the border of the lane/wedge region. No tubes were identified that could be attributed to the leakage observed during operation.
The licensee indicated that they used the Mitsubishi Intelligent probe and high-speed rotating pancake coil probe to examine approximately 100 tubes in SG B. The licensee indicated that the data had not been analyzed and they were only analyzing the flaw region to see if it was detectable with these probes.
Six tubes were in-situ pressure tested during this outage. One of these tubes contained a freespan flaw (discussed above) in SG A, and five tubes contained flaws in the re-roll region.
The licensees in-situ pressure testing criteria used flaw length and voltage to determine whether an indication falls within a required zone for testing. During these tests, no tubes leaked when tested up to the 3P pressure limit.
As a result of this inspection, a preliminary estimate indicated that 76 tubes would require plugging in SG A and 43 in SG B.
The licensee requested a follow-up conference call with the staff as a regulatory commitment that the licensee made during the review of the re-roll repair amendment. The commitment requires the licensee to inform the staff if circumferential indications are identified in tubesheets. This conference call took place on October 23, 2002. The licensee stated that two circumferential indications were detected in the original roll in the upper tubesheet of SG B.
The licensee indicated that circumferential cracks were not identified in any of the rerolls. The licensee performed a best estimate leakage assessment assuming postulated large break loss-of-coolant accident loads. The licensee stated that the leak rate was determined to be 1.87 gallons-per-minute (gpm), which is less than the allowable leakage limit of 9 gpm. This leak rate incorporated leakage from the two circumferential cracks located in the original roll (1.47 gpm), circumferential indications identified above the roll (0.38 gpm), and leakage from sleeves and plugs (0.02 gpm).
Arkansas Nuclear One cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Mr. Mike Schoppman Framatome ANP, Richland, Inc.
Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 March 2001