Supplemental Request for Information - Braidwood Station MOD/50.59 InspectionML17018A430 |
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Braidwood ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
01/06/2017 |
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From: |
NRC/RGN-III |
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To: |
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Download: ML17018A430 (2) |
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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 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 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 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 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 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 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 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 Applicant'S 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 Applicant'S Environmental Report. Part 5 of 15 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 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 ML0617004032006-06-13013 June 2006 Groundwater Contamination ML0617003902006-06-13013 June 2006 Tritium Sample Results ML0617003952006-06-13013 June 2006 Site Surveying Matrix - Portions Outside the Scope of the Request ML0617004052006-06-13013 June 2006 Ground Water Contamination ML0617004022006-06-13013 June 2006 Portion Outside the Scope of the Request ML0617003872006-06-13013 June 2006 Tritium Sample Results ML0617003852006-06-13013 June 2006 within Last Year - Portions Outside the Scope of the Request ML0617003832006-06-13013 June 2006 Inadvertent Liquid Releases - Portions Outside the Scope of the Request ML0617003992006-06-13013 June 2006 S.A.F.E Tracking Board - Portions Outside the Scope of the Request ML0617003792006-06-13013 June 2006 Tritium Questions - Portions Outside the Scop of the Request 2023-02-01
[Table view] |
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January 6, 2017 NRC Supplement to NRC Letter - INFORMATION REQUEST FOR AN NRC TRIENNIAL PERMANENT MODIFICATIONS AND 10 CFR 50.59 BASELINE INSPECTION DATED November 4, 2016 (Hereafter Items referred to are from this NRC Letter).
NRC Supplemental Information Requests for - Braidwood Station The following Screenings and Evaluations are requested:
Screenings:
- BRW-S-2014-32, EC 394080, MSSV DICHARGE PIPING MODIFICATION, U-1
- BRW-S-2014-101, Addition of high point vents on the Unit 2 CS and SI systems to address GL 08-01 concerns
- BRW-S-2014-105, Use of shim stops with the hydraulic jacking system
- BRW-S-2014-121, Retention of Temporary Scaffold Installed in Support of Maintenance Beyond 90 Days
- BRW-S-2014-166, EC 399677, Rev. 000 - Relocation of SG Blowdown Orifice Plates Upstream of Valves 2SD054A-H (U-2)
- BRW-S-2015-96, EC 401228- Installation of Reactor Head Stand, Bio shield Wall Extension, and Shielded Door Assembly inside Unit 2 Containment
- BRW-S-2015-138, Installation of a Relief Valve in Primary Containment Penetration P-71 for GL 96-06 Compliance and UFSAR DRP 16-040
- BRW-S-2015-149, SX STRAINER BACKWASH PIPING REPLACEMENT
- BRW-S-2015-153, Pipe support 2SX08117X added per EC 403574
- BRW-S-2016-41, Replace RCP Main Flange Closure Bolts with Studs and HydraNuts
- BRW-S-2014-60, TB-13-7 REVEALS SSPS WIRING CHANGE NEEDED
- BRW-S-2014-64, COMED SWITCHYARD CHANGES AND UFSAR UPDATE
- BRW-S-2014-70, Screening will address the long standing unavailability of AR detector 0RE-AR045 per WO 1566441 and taking the detector out of poll.
- BRW-S-2014-89, DRP 15-054 associated with a UFSAR enhancement that was considered as part of IR 1313361 that reviewed NRC Inspection Manual Operating Experience Smart Sample OpESS) 2012/01 "High Wind Generated Missile Hazard".
- BRW-S-2014-92, Screening in support of TS Bases Change 14-002 to revise the bases for SR 3.8.1.14 by removing the exception to RG 1.9 and the requirement for a short duration demonstration of full load capability at rated power factor.
- BRW-S-2014-103, FP TREF BIAS Deviation found OOT during RCS Temp. Alignment
- BRW-S-2014-109, Procedure revision for to update setpoint to match actual plant setpoint.
- BRW-S-2014-138, SSPS Wiring changes needed to address Westinghouse Technical Bulletin TB-13-7
- BRW-S-2014-139, Revise UFSAR Table 8.1-1 and Section 8.3.1 to describe conformance with Branch Technical Position (BTP) ICSB 8 (PSB), "Use of Diesel-Generator Sets for Peaking."
- BRW-S-2015-6, the activity is a revision to BwAR 1/2-19-B10/B11. This procedure changes will remove the requirement to limit generator MW and MVAR after receipt of high temperature alarm for any Main Power Transformer.
- BRW-S-2015-35, EC 400609: As-Left Condition for Unit 1 DRPI M8 (1RD43R) A5 Coil Open
- BRW-S-2014-106, EC 394081, U 2 MSSV Vent Line Modification ADAMS Accession Number ML17018A430
- BRW-S-2014-107, UFSAR Change Package for clarification of the reference made to the 15.6.1 event.
- BRW-S-2014-150, Revision to 1/2BwOSR 0.1-1,2,3 and 1/2BwOSR 01-4 to incorporate a revised UHS temperature value.
- BRW-S-2015-14, EC 400711, Reduced Elongation Range for the U-1 Reactor Vessel Main Closure Studs.
- BRW-S-2015-18, 50.59 for DRP 15-117 to support a UFSAR change in Chapter 15 to account for TCD on the LB LOCA Analysis
- BRW-S-2015-130, Revised 0BwFSG-51 to allow the use of the Unit 2 diesel generator fuel oil day tanks as a source of fuel to the portable generators used for powering the alternate ventilation fans.
- BRW-S-2016-30, Resolve Insulation Requirements at BAC Program Flanges
- BRW-S-2016-53, Add Insulation to 2WE171A-2" in the Lower Cable Spreading Room
- BRW-S-2016-74, Revise Fuel Center Line Melt Temperature Limit per MUR analyses.
- BRW-S-2015-33, the proposed activity revises the admin limits of the SX running pump discharge temperatures of the shifty and daily operating surveillances for modes 1-3 and mode 4 back to the original limits of 100 F.
Evaluations:
- BRW-E-2015-64, Unit 1 Fukushima Flex Piping Connections for Auxiliary Feedwater
- BRW-E-2015-55 (associated Screening BRW-E-2015-54), UFSAR Revision for Reactor Head Lift - Polar Crane Single Failure Proof Equivalency per NEI 08-05 (Braidwood Unit 1)
- BRW-E-2015-110 (associated Screening BRW-E-2015-109), Design Change to install Westinghouse Safe Shutdown Seals in the Units 1&2 reactor coolant pumps described in ECs 401809 & 401810
- BRW-E-2014-120, Incorporation of PAD Code Version 4.0 for Byron BWD fuel rod design
- BRW-E-2016-14, REMOVE AF DIESEL AIR INTAKE ELBOW AND BLANK OFF TB AIR INTAKE
- BRW-E-2016-71, Modification of combustion air intakes for AF diesel engines 1AF01PB and 2AF01PB
- BRW-E-2016-20, Replace RCP under-frequency KF relays with circuit shield Type 81 relays to address ABB part 21 Notification of potential defect for KF Relay ZPA
- BRW-E-2016-31, Temporary design change to allow 2D DT/TA Loop - Two T-hot RTD Operation for Cycle 19 operation.
- BRW-E-2015-92, Westinghouse Ovation Digital Upgrade for Rod Control Logic Cabinet (N-1 Outage)
ADAMS Accession Number ML17018A430