E-Mailed NRC Information Request for Braidwood Station - IP71152 Documents and Support Requested for Onsite Review Sent 10/17/18 (DRS-M.Holmberg)ML18291B316 |
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Braidwood |
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10/17/2018 |
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NRC/RGN-III |
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Download: ML18291B316 (1) |
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Category:- No Document Type Applies
MONTHYEARML23137A0782023-02-0101 February 2023 Public -Byron and Braidwood Commitment 10 Audit Call Questions RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020 Proposed Changes to Decommissioning Trust Agreements ML19228A1562019-08-21021 August 2019 NRC-2017-000292 - Resp 1 - Interim (Formerly FOIA/PA-2017-0292), Agency Records Subject to the Request Are Enclosed (Released Set Interim Response 1 - NRC-2017-000292) ML19046A2222019-02-0808 February 2019 NRC-2019-000158 - Resp 1 - Final. Agency Records Subject to the Request Are Enclosed ML18291B3162018-10-17017 October 2018 E-Mailed NRC Information Request for Braidwood Station - IP71152 Documents and Support Requested for Onsite Review Sent 10/17/18 (DRS-M.Holmberg) ML17319A0762017-10-30030 October 2017 FOIA-2017-0677 - Resp 1 - Final. Agency Records Subject to Request Enclosed ML17117A6552017-04-13013 April 2017 E-Mailed Request for Information Dated 04/13/17 for Braidwood Station, Unit 2, Inservice Inspection (Msh) ML17034A3542017-02-0202 February 2017 Samuel Miranda Statement ML17018A4302017-01-0606 January 2017 Supplemental Request for Information - Braidwood Station MOD/50.59 Inspection ML15230A2362015-09-0303 September 2015 Tables 1 and 2 ML15106A7362015-04-23023 April 2015 Conference Call Submittals ML15071A1192015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2015-03-0202 March 2015 Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML14191B1482014-07-17017 July 2014 Updated Talking Points for July 17th Meeting with Exelon Regarding Braidwood and Byron AFW Cross-tie Amendment ML14188A2482014-07-0707 July 2014 AFW Cross-tie Amendment - Talking Points for Public Teleconference RS-14-138, Enclosuresponses to Requests for Additional Information Re Environmental RAI AQ-11 to AQ-15 (as Amended by Exelon Generation Letter RS-14-283)2014-04-30030 April 2014 Enclosuresponses to Requests for Additional Information Re Environmental RAI AQ-11 to AQ-15 (as Amended by Exelon Generation Letter RS-14-283) ML14007A0902013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 7 of 15 ML14007A0942013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 10 of 15 ML14007A0892013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 14 of 15 ML14007A0882013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 13 of 15 ML14007A0832013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 2 of 15 ML14007A0842013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicants Environmental Report. Part 3 of 15 ML14007A0852013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicants Environmental Report. Part 5 of 15 ML14007A0922013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 and 2 License Renewal Application, Byron Station Applicant'S Environmental Report. Part 9 of 15 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1024506922010-09-0101 September 2010 EC 361017, Revision a, Evaluation of the Interim Remedial Action Pumping System ML1024506892010-09-0101 September 2010 EC 360234 Evaluation, Braidwood Station ML1024506882010-09-0101 September 2010 EC 360234, Eval - Mech, Braidwood Station ML1019702832010-06-16016 June 2010 EC 361965, Rev. 00 - Remediation of Tritium Contaminated Groundwater in the Vicinity of Vacuum Breaker #1 ML1019702802010-06-16016 June 2010 Attachment 2, Complex Troubleshooting, MA-AA-716-004, Revision 9 ML1017301232010-06-0909 June 2010 Green Ticket Tritium Releases ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0924506942009-09-0101 September 2009 Supplemental Document Request to Support Baseline ISI Inspection Procedure 71111.08 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 RS-08-010, Additional Information Supporting Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program2008-01-31031 January 2008 Additional Information Supporting Request for Amendment to Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0634705992006-12-14014 December 2006 Plant Service List ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0618403682006-06-27027 June 2006 Special Format for Chairman'S Back Q&A'S ML0617003992006-06-13013 June 2006 S.A.F.E Tracking Board - Portions Outside the Scope of the Request ML0617003832006-06-13013 June 2006 Inadvertent Liquid Releases - Portions Outside the Scope of the Request ML0617003852006-06-13013 June 2006 within Last Year - Portions Outside the Scope of the Request ML0617003872006-06-13013 June 2006 Tritium Sample Results ML0617004032006-06-13013 June 2006 Groundwater Contamination ML0617003792006-06-13013 June 2006 Tritium Questions - Portions Outside the Scop of the Request ML0617003762006-06-13013 June 2006 Contracts Made Braidwood ML0617004022006-06-13013 June 2006 Portion Outside the Scope of the Request ML0617004052006-06-13013 June 2006 Ground Water Contamination 2023-02-01
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NRC Information Request (10-17-2018) - IP 71152 - Braidwood Station -
Documents and Support Requested for Onsite Review.
On November 19, 2018, the NRC will conduct an inspection sample (Annual Follow-Up of Selected Issues) in accordance with IP 71152 Problem Identification and Resolution (1 Sample). The sample selected is associated with a 10CFR Part 21 notification Westinghouse made to the NRC (Westinghouse LTR-NRC-18-34, dated May 23, 2018). The specific issue is associated with wear of thermal sleeves in the control rod drive mechanism (CRDM) penetration tubes which could have a safety consequence that was not previously considered.
In order to minimize the impact to your onsite resources, and to ensure a productive inspection, please provide copy of the documents below to the NRC Resident Office on or before the entrance meeting scheduled for November 19, 2018. Please direct questions on this request to the lead inspector Mel Holmberg at msh@nrc.gov or 630 829-9748.
Documents/records that demonstrate completion of, or implementation of, actions identified in letter MRP-2018-027 NEI 03-08 Needed Inspection Guidance for PWR CRDM Thermal Sleeve Wear dated August 31, 2018. The documents requested apply to each Unit and should include applicable:
- a. Corrective action records with completed and planned actions to resolve the issue (e.g. AR 04140602 Westinghouse Part 21 For Control Rod Drive Mechanism Thermal Sleeves and AR 04141002 Followup Westinghouse Part 21 For Control Rod Drive Mechanism Thermal Sleeves).
- b. Thermal sleeve examination and measurement records (e.g. examination results for each CRDM thermal sleeve including a copy of the examination and/or measuring procedures applied to obtain these results).
c.
History of thermal sleeve or guide funnel repairs and impact on thermal sleeve wear measurements.
- d. Drawings of thermal sleeve and reactor head configurations that support examinations completed on the thermal sleeves.
- e. Analysis/evaluations completed on thermal sleeve wear to include wear rates measured or calculated for each thermal sleeve location in both Units.
f.
Acceptance criteria applied for thermal sleeve wear and the basis for this criteria (e.g. PWROG-16003-P or plant specific criteria).
- g. Thermal sleeve inspection schedule, reinspection schedule and the basis for these schedules.
- h. Thermal sleeve mitigation or repair plans.
i.
Evaluations of the potential impact of this issue on existing NRC commitments to aging management programs that support your license renewal application.
j.
Estimate of the Effective Full Power Years (EFPY) of operation for each Braidwood Unit as of August 2018.
ADAMS Accession Number: ML18291B316