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MONTHYEARML21168A1492021-06-0909 June 2021 Annual Meeting Attendees List ML20261H6032020-09-17017 September 2020 C-10's Certificate of Service for Motion for Leave, Reply to Oppositions and Exhibit INT053 ML20008D2232020-01-0808 January 2020 NRC Region I Twitter Feeds 10-1 to 12-31-2019 ML18136A8602018-05-16016 May 2018 02-2018 Aam NRC Staff List ML16349A1752016-12-21021 December 2016 MSFHI - Tables 1 and 2--Final 12-21-16 ML16203A4022016-06-15015 June 2016 06-15-16 - Publicly Available Documents Provided to Senator Markey in Response to His Letter Dated February 17, 2016, Pertaining to the Seabrook Station UFSAR Revisions 11, 12, 13, 14, and 15 ML16161A5872016-05-17017 May 2016 05-17-16, List of Publicly Available Documents Provided to Senator Edward Markey from Eugene Dacus, OCA Pertaining to the Seabrook Station UFSAR Revision 16 ML16146A1932016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting - Meeting Attendance List ML16118A2112016-04-19019 April 2016 04-19-16 - List of Publicly Available Documents Provided to Senator Markey in Response to His Letter Dated February 17, 2016, Pertaining to the Seabrook Station UFSAR Chapter 3 ML16071A4422016-03-0606 March 2016 Receipt of External Hard Drive Containing Revised I/O Files from NextEra Seabrook Station Nuclear Power Plant Flood Hazard Re-evaulation Report (CAC MF36782) SBK-L-15120, Independent Spent Fuel Storage Installation (ISFSI) Ics/Eals2016-02-27027 February 2016 Independent Spent Fuel Storage Installation (ISFSI) Ics/Eals ML15072A0372015-03-0909 March 2015 Enclosures 1 and 2 - Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years and Affidavit ML14209A0262014-07-28028 July 2014 2014 Seabrook Annual Assessment Meeting Attendance List Sheet ML14182A3382014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group H, Records Being Released in Their Entirety ML14182A1362014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group I, Records Being Released in Part ML14182A1322014-06-30030 June 2014 FOIA/PA-2013-0332 - Resp 6 - Partial, Group G, Records Already Publicly Available ML14141A6272014-05-20020 May 2014 LTR-14-0288-Ticket - Senator Edward J. Markey Ltr. Information About NRC-Sanctioned Job Shadow Program with China ML14113A0582014-04-18018 April 2014 LTR-14-0224-Ticket - Senator Edward J. Markey and Senator Elizabeth Warren Ltr. Measures Needed to Protect Pilgrim Nuclear Power Station and the Seabrook Station Against Seismic Vulnerability ML15161A0402014-02-19019 February 2014 Draft Vital Inverter NOED 02191 SBK-L-14006, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 3 of 32014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 3 of 3 ML14034A0212014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 2 of 3 ML14034A0202014-01-22022 January 2014 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application Severe Accident Mitigation Alternatives Review. Part 1 of 3 ML15236A2732014-01-16016 January 2014 We the People, a National Whistleblower Organization ML14007A7152014-01-0707 January 2014 G20140030/LTR-14-0009-Ticket - Senator Jeanne Shaheen Email Seabrook - Piping/Plumbing (Constituent Correspondence) ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13354B9542013-12-18018 December 2013 G20140055/LTR-13-0957-Ticket - Senator Edward Markey, Et Al., Ltr Requests the NRC Make No Decision on the 6/1/10, Request for the Seabrook Nuclear Power Plant for a 20 Year Operating License Until the Concrete Degradation Is Well Tested an ML13354C0052013-12-18018 December 2013 G20140010/LTR-13-0959-Ticket - Bert Knowles Ltr. Opposition for the Relicensing of the Seabrook Nuclear Plant ML12174A0332012-06-0404 June 2012 Region 1 Comments on Draft TIA for Seabrook ASR Issue ML12174A0462012-06-0404 June 2012 Preliminary Draft Response to Request for Technical Assistance for Seabrook Station Alkali-Silica Reaction Degradation of Concrete ML12131A3782012-05-10010 May 2012 Annual Assessment Meeting Signing Sheets April 2012 ML1211603332012-04-23023 April 2012 Detailed Questions for Seabrook ASR Public Meeting on April 23, 2012 ML12088A2142012-03-26026 March 2012 Concrete Degradation - Alkali Silica Reaction ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12054A6432012-02-16016 February 2012 Nextera Control of Contractors for ASR Issues ML12088A2132011-07-20020 July 2011 Concrete Degradation - Alkali Silica Reaction ML1117218982011-06-21021 June 2011 Annual Assessment Meeting Attendance List, June 8, 2011 ML1104802952011-02-15015 February 2011 Attachment to E-mail, Willoughby to Miller, NRC Conference Call on Friday - Seabrook Annulus Debris Interceptor Approach Velocity ML1100504852011-01-0505 January 2011 Attachment to E-mail, Kilby, to Miller, Information Related to Seabrook'S Proposed H License Amendment Request ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0927403272009-09-30030 September 2009 Seabrook Regulatory Conference Sign-in Sheets ML0913200902009-04-30030 April 2009 Annual Assessment Meeting Sign-in Sheet, 4/30/2009 ML0913305422008-11-0303 November 2008 Seabrook - Fire Protection of Safe Shutdown Capability (10CFR50, Appendix R, Revision 9 ML0810904032008-03-25025 March 2008 Annual Assessment Meeting Attendance List, 3/25/08 ML0808000362008-03-13013 March 2008 List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0731104102007-10-17017 October 2007 Enclosure 2 to Fple Letter SBK-L-06227 - Emergency Initiating Condition Matrix, Modes 1, 2, 3, & 4 ML0731104072007-10-17017 October 2007 Enclosure 1 to Fple Letter SBK-L-06227 - Summary Explanation Providing the Necessary Justification for Changing the Basis of the Fple Seabrook Emergency Action Level (EAL) Scheme from NUREG-0654 to NEI 99-01, Revision 4 ML0731104132006-12-29029 December 2006 Enclosure 4 to Fple Letter SBK-L-06227 - Seabrook Emergency Classification System, Section 1-5.1 Through 1.5.11 ML0634705992006-12-14014 December 2006 Plant Service List 2021-06-09
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Region I Comments on Draft TIA for Seabrook ASR Issue General Comment:
Specific Comments:
- 1.
Reference:
Various sections throughout related to aging management and in particular Question No. 1.
- 2.
Reference:
Section 1.c refers to NRC letter of June 29, 2011.
inforniation in this record was deleted in accordance with the r.cdom of Information Act, exemnptionrs -
G1
- 3.
Reference:
Section 1 (e) on Aggressive Groundwater (b)(5) 4.--
Reference:
Section 1 (f) on how representative the concrete core samples are ifthey do go through wall to the exterior.
(b)(5)
- 6.
References:
Sections 1 (h) on ASR severity h
Short
Description:
The basis for this standard is not clear.
- 7.
References:
Sections 1 (i) on ASR Severity and the Use of Consultants Short
Description:
The basis for this standard is not clear.
- 8.
References:
Sections 2 (d) Global and Local building load analysis should be based on actual measured material properties base on the use of ACI 349.3R.
- 9.
References:
Sections 3 (a) and (b) deal with sampling methods for concrete cores and in-place methods to estimating concrete strength.
(b)(5)
- 10.
References:
Sections 3 (c) deals with sampling and representativeness of the samples to in-situ conditions.
'b)(5)'... ."
L,--ý0(ý
- 11.
References:
Sections 3 (d) need for a plan and the use of Consultants and Reference that may not be a part of the Current Licensing Basis (CLB).
ý4(b)(5)
- 12.
Reference:
Section 4 (d) on alkali reactivity testing of coarse aggregates
- 13.
Reference:
Section 4 (e) on the need to do stiffness damage tests Short
Description:
The regulatory basis for the suggested test not clear.
I(b)(5)
- 14.
Reference:
Section 4 (f) on the need to monitor in-situ temperature and humidity of buildings affected by ASR.
- 15.
Reference:
Section 4 on Regulatory Requirements
Excerpt ML11178A338 NRC Letter dated June 29, 2011 Follow-up RAI B2.1.31-1:
Background:
By letter dated April 14, 2011, the applicant responded to a staff RAI regarding concrete degradation due to groundwater in-leakage and the occurrence of Alkali-Silica Reaction (ASR) in the concrete, The applicant stated that an extent of condition investigation regarding the ASR degradation was on-going, along with the development of a long range aging management plan.
The applicant explained that the plan would not be fully developed and implemented until December 2013. The applicant's response also listed several American Society for Testing and Materials (ASTM) standards that would be used to estimate the ASR reaction rate.
Issue:
The applicant provided no specific information about the applicability of the original operability determination conducted when ASR was initially identified. The response also lacked specific information about what tests (laboratory and in-situ) would be conducted and when. The response also made no mention of how possible reductions in concrete shear strength were being estimated and addressed. In addition, the RAI response stated that cores were being taken in accordance with American Concrete Institute (ACI) 228.1 R-03; however, it did not address the statistical validity and size of core samples taken or planned at each location.
Request:
- 1. Explain if the current operability determination remains valid until the long term aging management plan is developed and implemented.
- 2. Explain how the concrete tests and evaluations performed so far can be used to establish a trend in degradation of the affected structures until the long term aging management plan is implemented.
- 3. Provide detailed and comprehensive information regarding the planned approach to addressing ASR degradation throughout the site. The description of the actions planned to test, evaluate, and mitigate ASR in the RAI response do not provide sufficient details for the staff to determine ifthe aging of the structures will be adequately managed during the period of extended operation.
At a minimum include a discussion of the following:
- a. The locations where monitoring or sampling will be conducted, and how these results will be used to address other susceptible locations.
- b. The frequency of the monitoring and sampling to establish a trend in degradation of the structures and rate of ASR, and why the provided frequency is adequate.
- c. Detailed information about the planned in-situ monitoring or testing and laboratory testing. This should include the test method, frequency, and schedule.
- d. How the number of concrete samples taken or planned from each structure will ensure statistical validity.
- e. How the length of core samples taken or planned will account for variation of ASR across the wall thickness.
- f. How the extent of degradation/corrosion of rebars will be established in the ASR affected areas during the period of extended operation.
- g. How the reduction in load carrying capacity in the steel embedments and anchors used to support equipment, piping, conduits, and other commodities will be established in the ASR affected areas during the period of extended operation.
- h. How the results of the petrographic examination will be used to determine quantitative damage in concrete and rate of degradation for the period of extended operation.
- i. Plans, if any, for relative humidity and temperature measurements of affected concrete areas over the long term.
- j. Plans to perform stiffness damage tests to estimate the expansion attained to date in ASR affected concrete.
- k. How the current and future rate of expansion of concrete will be determined to ensure that bond between the rebar and concrete is effective over the long term.
I. How the results of concrete compressive strength and modulus of elasticity conducted so far will be adjusted to account for future degradation during the period of extended operation.
- 4. Explain how the possibility of a reduction in shear strength capacity due to ASR degradation is being evaluated and addressed since core samples are not being used to establish the tensile strength of concrete. The response should include a discussion of how the possible reduction is being quantified and how the reduction is shown to be acceptable for the period of extended operation.