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Category:Meeting Summary
MONTHYEARML24248A0152024-09-0505 September 2024
Summary of August 28, 2024, Public Pre-Application Meeting with NextEra Energy Point Beach, LLC Regarding Assessing Seismic Risk
ML24227A5082024-08-15015 August 2024
Summary of the July 15, 2024, Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2
ML23199A0262023-07-18018 July 2023
Summary of Public Outreach to Discuss the NRC 2022 End of Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2
ML23118A1762023-05-0404 May 2023
– Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191
ML22144A0022022-09-14014 September 2022
Summary of February 16, and May 18, 2022, Meetings with Nextera Energy/Florida Power & Light Company Regarding Planned Submittal of License Amendment Request for a Common Fleet Emergency Plan
ML22181B1182022-06-30030 June 2022
Summary of the June 23, 2022, Public Outreach to Discuss the NRC 2021 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2
ML22019A2792022-01-20020 January 2022
Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant
ML22004A0772022-01-0606 January 2022
Summaries of December 8, 2021 Draft Supplemental Environmental Impact Statement for Subsequent License Renewal Application Public Meetings
ML21295A2532021-10-26026 October 2021
Summary of Public Webinar with NextEra Energy Point Beach,Llc Regarding Proposed Future LAR to Adopt TSTF-505, Rev.2, Provide Risk Informed Extended Completion Times-RITSTF Initiative 4B, at Point Beach Plant, Units 1&2 (L-2021-LRM-0086)
ML21288A1222021-10-20020 October 2021
SLRA Summary of August 5, 2021, Public Meeting on Proposed Aging Management Activities of Irradiated Concrete and Steel Reactor Vessel Supports
ML21214A1512021-08-27027 August 2021
SLRA June 3, 2021, Public Meeting - Proposed Aging Management Activities of Irradiated Concrete and Steel Reactor Vessel Supports
ML21214A1652021-08-27027 August 2021
SLRA June 30, 2021, Public Meeting - Proposed Aging Management of Reactor Vessel Internals
ML21161A2992021-06-17017 June 2021
Summary of May 18, 2021 Public Webinar with Nextera Energy Point Beach, LLC Regarding Path Forward for Generic Letter 2004-02 Closure
ML21166A2192021-06-15015 June 2021
Summary of June 10, 2021, Public Webinar to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of the Point Beach Nuclear Plant
ML21148A1162021-06-0101 June 2021
SLRA Public Meeting Discussion Questions 6-3-21
ML21075A3422021-03-17017 March 2021
Meeting Summary: Public Scoping Meeting for the Environmental Review of the Subsequent License Renewal Application for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (EPID No.: L-2020-SLE-0002) - Memo
ML21075A3432021-02-17017 February 2021
Meeting Summary: Public Scoping Meeting for the Environmental Review of the Subsequent License Renewal Application for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (EPID No.: L-2020-SLE-0002) - Summary
ML20253A1382020-09-11011 September 2020
8/13/2020 Summary of Public Meeting with NextEra Energy Point Beach, LLC Regarding Proposed License Amendment Request for Point Beach Nuclear Plant, Unit 1, Containment Building Truss License Condition Change Due to COVID-19
ML20233A7902020-08-20020 August 2020
Summary of the July 30, 2020, Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center and the Point Beach Nuclear Plant
ML19344A0162019-12-12012 December 2019
Summary of Pre-Application Public Teleconference with Nextera Energy Point Beach, LLC, for Point Beach Nuclear Plant, Units 1 and 2
ML19246A6242019-09-10010 September 2019
Summary of August 14, 2019, Pre-Application Public Teleconference with NextEra Energy Point Beach, LLC, for Point Beach Nuclear Plant, Unit 2
ML19179A0662019-07-17017 July 2019
Summary of Closed Meeting with Nextera Energy, LLC, to Discuss Security-Related Information for Point Beach Nuclear Plant, Unit 1 and 2, and Duane Arnold Energy Center
ML19095B7772019-04-0505 April 2019
Summary of Public Outreach/Open House to Discuss the NRC 2018 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2
ML18220B0192018-08-13013 August 2018
7/12/2018 Summary of Meeting with NextEra Energy Point Beach, Llc. to Discuss Supplemental Response to the RAI for Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit 1 and 2 (CAC Nos. MF9532 & MF9533; .
ML18179A4032018-06-29029 June 2018
Public Meeting Discussion Points
ML18136A9052018-05-31031 May 2018
Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02
ML18141A8452018-05-29029 May 2018
Summary of May 1, 2018 Meeting with NextEra Energy Point Beach, LLC, to Discuss License Amendment Request for High Winds Probabilistic Risk Assessment for Point Beach Nuclear Plant, Unit Nos. 1 and 2
ML18121A3142018-05-0101 May 2018
Summary of the April 10, 2018 Public Outreach/Open House for the NRC to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Point Beach Plant, Units 1 and 2
ML17346A9122017-12-22022 December 2017
Summary of November 14, 2017 Public Teleconference with NextEra Energy Point Beach, LLC, to Discuss Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (CAC Nos. MF9532 and MF9533; EPID L-2017-L
ML17310B2062017-11-20020 November 2017
Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02
ML17216A1732017-09-0707 September 2017
Notice of Meeting with Florida Power & Light Company and NextEra Energy to Discuss Closing Out Generic Safety Issue-191 and Generic Letter 2004-02
ML17202U7272017-07-19019 July 2017
Summary of July 11, 2017, Open House to Discuss the 2016 End-Of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2
ML16305A3882016-11-0808 November 2016
Summary of October 18, 2016 Meeting with Nextera Energy Point Beach, Llc, to Discuss Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (TAC Nos. MF8403 and MF8404)
ML16160A1742016-06-0707 June 2016
Summary of Public Meeting with Nextera Energy Point Beach, LLC to Discuss the 2015 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant Units 1 and 2
ML15341A0182015-12-16016 December 2015
Summary of Closed Pre-Application Teleconference with Nextera Energy Point Beach Regarding Steam Generators H* License Amendment Request
ML15217A3312015-08-26026 August 2015
July 28, 2015, Summary of Ublic Meeting with NextEra Energy Point Beach, LLC, to Discuss a Proposed Licensing Basis Change for the Turbine-Driven Auxiliary Feedwater Pumps at the Point Beach Nuclear Plant, Units 1 and 2
ML15215A0502015-08-0505 August 2015
Summary of Public Meeting with NextEra Energy Point Beach, LLC, to Discuss Proposed Changes to Containment Dome Truss Design Bases Code for Point Beach Nuclear Plant, Units 1 and 2
ML15121A0572015-05-15015 May 2015
June 9 - 12, 2014 Summary of Audit at Point Beach Nuclear Plant, Unit Nos. 1 and 2, Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805
ML15113B3862015-04-23023 April 2015
April 20, 2015 Summary of Public Outreach/Open House to Discuss the NRC 2014 End-Of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant
ML15106A7122015-04-23023 April 2015
Summary of April 6, 2015, Meeting with NextEra Energy Point Beach, LLC, to Discuss License Amendment Request to Transition to NFPA 805
ML14114A1002014-04-23023 April 2014
Summary of Public Meeting to Discuss 2013 Annual Assessment Results for Point Beach Nuclear Plant
ML13192A1432013-07-10010 July 2013
6/26/2013 - Summary of Open House to Discuss the 2012 Point Beach Nuclear Plant End-Of-Cycle Performance Assessment
ML1212805092012-06-18018 June 2012
May 1, 2012 - Summary of Teleconference with Performance Contracting, Inc., Regarding Large Flume Testing for Point Beach Nuclear Plant
ML11173A2332011-06-22022 June 2011
Summary of Public Meeting with NextEra Energy Point Beach, LLC to Discuss the Point Beach Nuclear Plant End-of-Cycle Performance Assessment for 2010
ML1108208272011-04-21021 April 2011
Summary of Pre-application Meeting with NextEra Energy, Inc., and Florida Power & Light Company, on Turkey Point, Units 3 and 4, St. Lucie, Units 1 & 2, Point Beach, Units 1 & 2, Duane Arnold Transition to NFPA-805
ML1014000432010-05-20020 May 2010
Summary of Public Meeting with FPL Energy Point Beach, LLC to Discuss Progress on the Nuclear Excellence Model and Updates on Operational Excellence, Generation Reliability, and Organizational Effectiveness at Point Beach
ML1012502352010-05-0505 May 2010
Summary of the April 22, 2010, Public Meeting to Discuss the 2009 Point Beach End-of-Cycle Performance Assessment
ML0924305212009-08-31031 August 2009
July 29, 2009,Summary of Public Meeting to Discuss the Progress on Actions Taken in Response to Substantive Cross Cutting Issues and the Results of an Independent Assessment of Corrective Actions for Recent Nuclear Safety Culture Surveys
ML0914001932009-05-20020 May 2009
Summary of Public Meeting to Discuss the Progress on Actions Taken in Response to a Nuclear Safety Culture Survey in 2008 - Point Beach Nuclear Plant
ML0832308202008-11-20020 November 2008
Teleconference Summary Regarding the 2008 Steam Generator Tube Inspection Results
2024-09-05
[Table view]
Category:Note
MONTHYEARML13193A0322013-07-11011 July 2013
Additional Equipment Height Information with Vulnerability to Flood Waters
ML0832308202008-11-20020 November 2008
Teleconference Summary Regarding the 2008 Steam Generator Tube Inspection Results
ML0816908552008-07-0202 July 2008
Telconference Summary Regarding Point Beach Nuclear Plant Proposed Power Uprate and Alternate Source Term Amendment
ML0515202522005-05-24024 May 2005
2SI 825B Not Full Open
ML0514604102005-05-24024 May 2005
Exit Notes - Holmberg, Riii, Bilik, Riii
ML0514604122005-05-24024 May 2005
Exit Notes Holmberg, Riii
ML0514604162005-05-24024 May 2005
Exit Notes Pederson, Riii, Holmberg, Riii, Bilik, Riii
ML0514700762005-05-24024 May 2005
Note from Individual with 05/27/2004 E-Mail from J. Petrosino, NRR, to H. Heller, Riii
ML0515201462005-05-24024 May 2005
Sludge Lance and Phone Line Through Containment Hatch While Fuel Movement in Progress
ML0515201512005-05-24024 May 2005
Gas Turbine Reliability Not Meeting FSAR Requirements
ML0515202122005-05-24024 May 2005
Questions and Notes
ML0515202552005-05-24024 May 2005
Rio Entry 191 Note
ML0515202562005-05-24024 May 2005
Outage Stand Down Observations
ML0515202602005-05-24024 May 2005
Handwritten Notes
ML0508800462005-03-22022 March 2005
Notes for Entrance Meeting
ML0508400652005-03-21021 March 2005
Briefing Notes for RCS Vent Path Issue
ML0505601182005-02-24024 February 2005
Letter from M. Lintz to File Transmitting e-mail to Point Beach Nuclear Plant
ML0502701212005-01-25025 January 2005
Summary of Telephone Conference Held on January 05, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502606992005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502602372005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, Llc, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502602472005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502603192005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502603592005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502606362005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0502700372005-01-19019 January 2005
Summary of Telephone Conference Held on January 14, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plant,
ML0502700462005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear
ML0502604732005-01-19019 January 2005
Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units
ML0500601672004-12-16016 December 2004
Summary of Telephone Conference Held on December 15, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC Concerning Draft Requests for Additional Information Pertaining to the Point Beach, Units 1 & 2...
ML0430206312004-10-28028 October 2004
Summary of Conference Call with Nuclear Management Company, LLC (NMC) to Discuss Responses to the Severe Accident Mitigation Alternatives (SAMA) Requests for Additional Information (Rais)
ML0414602652004-08-0909 August 2004
Summary of Scoping & Screening Group Methodology Audit Preparation Visit Between the NRC & NMC -Concerns Receipt of Requested Staff Documentation for Audit Preparation for the Point Beach Nuclear Plant, Units 1 & 2, LRA
ML0515204662004-08-0404 August 2004
Outage Inspection Notes
ML0414203162004-05-21021 May 2004
Handwritten Comment Handed to Point Beach Resident Inspector from Cassandra Dixon
ML0412801022004-05-0606 May 2004
Note 05/06/2004 to All Region III Facility Training Managers Re Reprint of NRC Form 396
ML0508700512004-04-19019 April 2004
Note to U1R28 Shift Outage Managers from Sr. Management Representative, Work Prior to and During Outage Briefing
ML0508700502004-04-19019 April 2004
Shift Outage Manager - Days
ML0402300912004-02-10010 February 2004
Memo to File Re Facsimile Transmission for Issue Discussed in Telephone Conference
ML0308005832002-11-22022 November 2002
1 Page of Handwritten Notes
ML0626801962002-07-0303 July 2002
Note to J. Heller from M. Kunowski (Rill) Re Kewaunee and Point Beach Plants
ML0627904142002-06-27027 June 2002
Typed Notes of Phone Call Conversation with Lynn Bartleme, Dznps at Point Beach
ML0627903882002-02-23023 February 2002
Individual Interview Regarding Fitness-for-Duty Concern at Kewaunee During a Refuel Outage in 2001
ML0626405682001-11-12012 November 2001
Note to Allegation File from J. Heller, Telephone Contact with Al Capristo, Nuclear Management Company.
ML0626801922001-11-0808 November 2001
Note to: USNRC Region III from Anonymous with Handwritten Notes
2013-07-11
[Table view] |
Text
December 16, 2004 LICENSEE: Nuclear Management Company, LLC FACILITY: Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON DECEMBER 15, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference on December 15, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant, Units 1 and 2, license renewal application. The conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the meeting participants. Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Michael J. Morgan, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosures:
As stated cc w/encls: See next page
ML050060167 DOCUMENT NAME: E:\Filenet\ML050060167.wpd OFFICE PM:RLEP SC:RLEP NAME MMorgan SLee DATE 12/22/04 12/22/04 Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esq. Mr. Jeffrey Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. Frederick D. Kuester David Weaver President and Chief Executive Officer Nuclear Asset Manager We Generation Wisconsin Electric Power Company 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 James Connolly John Paul Cowan Manager, Regulatory Affairs Executive Vice President & Chief Nuclear Point Beach Nuclear Plant Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 6610 Nuclear Road 700 First Street Two Rivers, WI 54241 Hudson, WI 54016 Mr. Ken Duveneck Douglas E. Cooper Town Chairman Senior Vice President - Group Operations Town of Two Creeks Palisades Nuclear Plant 13017 State Highway 42 Nuclear Management Company, LLC Mishicot, WI 54228 27780 Blue Star Memorial Highway Covert, MI 49043 Chairman Public Service Commission Fred Emerson of Wisconsin Nuclear Energy Institute P.O. Box 7854 1776 I Street, NW., Suite 400 Madison, WI 53707-7854 Washington, DC 20006-3708 Regional Administrator, Region III Roger A. Newton U.S. Nuclear Regulatory Commission 3623 Nagawicka Shores Drive 801 Warrenville Road Hartland, WI 53029 Lisle, IL 60532-4351 James E. Knorr Resident Inspector's Office License Renewal Project U.S. Nuclear Regulatory Commission Nuclear Management Company, LLC 6612 Nuclear Road 6610 Nuclear Road Two Rivers, WI 54241 Point Beach Nuclear Plant Two Rivers, WI 54241
DISTRIBUTION: Ltr. to Licensee: Nuclear Management Company, LLC, Re: Pt. Beach Nuclear Plant, Units 1 and 2, Dated: Dece,ber 16, 2004 Adams accession no.: ML050060167 HARD COPY RLEP RF Project Manager E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li M. Itzkowitz (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff P. Lougheed, RIII J. Strasma, RIII A. Stone, RIII H. Chernoff W. Ruland C. Marco L. Raghavan T. Mensah OPA
LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE TO DISCUSS THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION DECEMBER 15, 2004 Participants Affiliations J.Knorr Nuclear Management Company, LLC J.Thorgersen Nuclear Management Company, LLC T.Mielke Nuclear Management Company, LLC M.Morgan Nuclear Regulatory Commission M.Murphy Nuclear Regulatory Commission V.Rodriguez Nuclear Regulatory Commission Enclosure 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION December 15, 2004 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on December 15, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant, Units 1 and 2, license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.
Aging Management Review Program D-RAI 3.1-1 Table 3.1.2-5 identifies that aging will be managed for the SG Anti-Vibration Bars (AVBs) by the Water Chemistry Program and the Steam Generator Integrity Program for cracking due to SCC. Table 3.1.2-5 also refers to NUREG 1801, Volume 2, line item (IV.D1.2-h) and table 1 line item (3.1.1-19) which refer to loss of material associated with FAC for this line item.
Provide an explanation for the discrepancy between the aging effect identified in the license renewal application and what is identified in GALL (including the further evaluation section of the LRA) and provide any corrections. Discuss how SG secondary side inspections will be used to assess degradation in the AVBs in light of the ten elements of an AMP.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.1-2 Table 3.1.2-5 identifies that aging management for a number of SG secondary side components which are identified as susceptible to loss of material will be provided by both the Water Chemistry Program and Steam Generator Integrity Program. Table 3.1.2-5 also associates NUREG 1801 Volume 2 line item (IV.D1.1-c) and table 1 line item (3.1.1-02) with these components which identifies that the Inservice Inspection Program along with Water Chemistry will be used to manage aging. The further evaluation (item 3.1.2.2.2.1) associated with (3.1.1-02) for these items indicates Inservice Inspection and Water Chemistry will manage aging for these components and that the Steam Generator Integrity Program will provide all inclusive guidance for the management of Steam Generator assets. The Steam Generator Integrity Program description does not indicate that it will be used to meet the intent of the Inservice Inspection program for certain components. Clarify if the SG Integrity Program is intended to subsume the Inservice Inspection activity and manage aging of these components, why Inservice Inspection is not addressed in table 3.1.2-5 for these components and how the Steam Generator Integrity Program will manage aging for these components with particular focus being paid to addressing detection, monitoring and trending, acceptance criteria and operating experience with past secondary side inspections associated with these components.
Also address how loss of material, pitting and crevice corrosion of the shell and its components will be identified by these secondary side inspections.
Enclosure 2
SG Blowdown Piping Nozzles and Secondary Shell Penetration SG Feedwater Nozzle SG Secondary Closures SG Steam Outlet Nozzle SG Tube Bundle Wrapper and Wrapper Support System SG Tubesheet SG Upper and Lower Shell, Elliptical Head and Transition Cone Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.1-3 Table 3.1.2-5 indicates that SG Components (in contact with primary water) fabricated from stainless steel, alloy 600 and alloy 690 are susceptible to loss of material and the aging will be managed by Water Chemistry alone. Since water chemistry is a mitigative strategy and inspection is used (one time inspection at a minimum) to verify its effectiveness, provide a list of the subject sub-components and provide an explanation why water chemistry alone is sufficient to manage aging in these sub-components based on specific operating experience or past inspection results of these sub-components demonstrating the effectiveness of water chemistry.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.1-4 Table 3.1.2-5 indicates that the SG Divider Plate which is fabricated from alloy 600 and alloy 690 is susceptible to stress corrosion cracking and the aging will be managed by Water Chemistry alone. Since water chemistry is a mitigative strategy and inspection is used (one time inspection at a minimum) to verify its effectiveness, provide an explanation why water chemistry alone is sufficient to manage aging in these components based on specific operating experience or past inspection results that demonstrate the effectiveness of water chemistry.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.1-5 Clarify the SG program scope to identify those sub-components that rely on this program for aging management. Discuss the periodicity, acceptance criteria and bases for these items associated with the secondary side SG inspections for the various sub-components which rely on this program for aging management.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Enclosure 2
D-RAI 3.1-6 The SG Integrity Program AMP related operating experience acknowledges the Outside Diameter Stress Corrosion Cracking (ODSCC) that was identified at Seabrook and indicates that the Point Beach Nuclear Power Plant SG tube material is thermally treated alloy 600 in Unit 1 and thermally treated Alloy 690 in Unit 2. Provide an operating experience discussion regarding inspections and results performed at Point Beach Units 1 & 2 to identify if similar tube eddy current characteristics exist as those identified at Seabrook and documented in Supplement 1 of NRC Information Notice 2002-21.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Aging Management Program B2.1.7 - Buried Services Monitoring Program D-RAI B2.1.7-1 The program indicates that buried components within the program scope are coated per industry practice prior to installation. Although the AMP references industry practice what bases were used by the plant to confirm that all buried services within the program scope were required to be coated at the plant? If such documentation does not exist, how is reasonable assurance established that program components are all coated in light of the limited related operating experience.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.7-2 Related operating experience indicates that a post-indicating valve was repaired in the fire protection system which required excavation, exposing portions of the associated piping. The operating experience also indicates that the external portion of the piping showed no signs of corrosion after 14 years. Please discuss how the specific condition assessment of the piping corrosion (or lack of) was made in light of the program element that buried components are coated per industry practice; i.e., was the piping coated and was the coating removed to make this assessment?
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.7-3 Since this is a new program it is understandable that there may be limited operating experience regarding inspections of opportunity which validate the limited buried component degradation.
However, the GALL indicates that inspection periodicity needs to be evaluated on a plant specific bases. With such a limited amount of experience, provide a justification why one time inspection of various in-scope components is not warranted prior to the period of extended Enclosure 2
operation to establish a sound basis for inspection frequency or to justify why inspections of opportunity will adequately manage aging in the future.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Aging Management Program B2.1.22 - Tank Internal Inspection Program D-RAI B2.1.22-1 The Tank Internal Inspection Program indicates that the internal surfaces of carbon steel tanks will be periodically visually inspected and UT will be used to inspect inaccessible areas, such as the tank bottom or may be used from external surfaces. Provide a discussion regarding the periodicity and its bases for internal visual inspection and UT inspection of the tank bottoms.
Discuss the inspection scope for internal visual, UT of the tank bottom and when external UT is used, for instance; will internal visual inspection consist of 100% of the tank surface area, will the tank bottom UT consist of 100% of the bottom surface and if 100% inspection is not performed discuss the bases for a reduced inspection scope and the associated expansion criteria. Discuss how external UT examination scope will be comparable to internal visual examination scope when external UT inspection is used in lieu of internal inspection. If a sampling strategy is used in any of the above inspections provide a discussion of the sampling plan and its bases.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.22-2 Since monitoring and trending will only commence if significant wall loss is identified, how will it be possible to know the areas monitored if 100% inspection is not performed every time and how will accurate rates of degradation be determined which could be used to establish alternate inspection frequencies as outlined in the program description. The Acceptance Criteria indicates that Any degradation will be recorded and evaluated... this appears to be a form of monitoring and trending, discuss the apparent discrepancy.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.22-3 Define what is considered significant coating degradation which would lead to corrective action or significant material loss which would lead to commencement of trending. How will loss of material be measured/evaluated when visual inspection is performed to determine level of significance. Discuss how loss of material from general corrosion, pitting or underdeposit attack would be addressed relative to significant material loss and acceptance criteria.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Enclosure 2
D-RAI B2.1.22-4 Based on the related operating experience, tank internal inspections of the North and South Condensate Tanks have occurred, did these inspections include UT of the tank bottoms. If the tanks bottoms were not evaluated when will the tank bottoms be evaluated and what was the justification for not evaluating the bottoms. Had these tanks ever been recoated in the life of the plant and when was the previous inspection of each of these tanks.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Enclosure 2
