E-Mailed Request for Information for Byron Station, Unit 2, on 03/27/19 (DRS-M.Holmberg)ML19087A148 |
Person / Time |
---|
Site: |
Byron |
---|
Issue date: |
03/27/2019 |
---|
From: |
NRC/RGN-III |
---|
To: |
|
---|
References |
---|
Download: ML19087A148 (3) |
|
Similar Documents at Byron |
---|
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 ML19087A1482019-03-27027 March 2019 E-Mailed Request for Information for Byron Station, Unit 2, on 03/27/19 (DRS-M.Holmberg) ML17319A0762017-10-30030 October 2017 FOIA-2017-0677 - Resp 1 - Final. Agency Records Subject to Request Enclosed ML17047A6902017-02-14014 February 2017 E-Mailed; Byron Station, Unit 1 - Request for Information Sent 02/14/17 (Msh) ML17034A3542017-02-0202 February 2017 Samuel Miranda Statement 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 ML14192B4132014-07-0808 July 2014 Email -- Byron License Renewal Request for Information ML14188A2482014-07-0707 July 2014 AFW Cross-tie Amendment - Talking Points for Public Teleconference ML15349A5962014-07-0303 July 2014 Secured Transportation Services (Sts), Truck Route Approval Request, Byron to Idaho National Laboratory ML14007A0912013-12-19019 December 2013 Response to NRC Request for Additional Information, Dated November 21, 2013, Related to the Byron and Braidwood Stations, Units 1 & 2 License Renewal Application, Byron Station Applicant'S Environmental Report - Cooling System Blowdown..... 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 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 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 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 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 ML13134A1512013-07-16016 July 2013 License Renewal Application Review Schedule ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1110301882011-04-0808 April 2011 Enclosure 3 - Dose Estimates ML1017301212010-06-0909 June 2010 Pre-release Inspection Results ML1017301222010-06-0909 June 2010 Tritium Inspection ML0921603172009-07-30030 July 2009 ISI 07/30/2009 Request for Information ML0910304462009-04-0202 April 2009 Requests for Relief for Alternate Examination Frequency, Attachment 5, Metallurgical Evaluations of a 'Boat' Sample from the #68 CRDM Penetration on Byron Unit 2 RS-09-050, Byron, Unit 2 - Requests for Relief for Alternate Examination Frequency - Attachments 1 Through 42009-04-0202 April 2009 Byron, Unit 2 - Requests for Relief for Alternate Examination Frequency - Attachments 1 Through 4 ML0910304452009-04-0202 April 2009 Requests for Relief for Alternate Examination Frequency - Attachments 1 Through 4 ML0825401652008-09-10010 September 2008 RFI 09/10/08--Byron Hut IP 71152 Request for Information 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 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 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 ML0634705992006-12-14014 December 2006 Plant Service List ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0629003742006-06-19019 June 2006 Final As-Administered Administrative Jpms for the Byron Initial Examination - June 2006 ML0606504612006-02-28028 February 2006 Region III NRC Tritium Inspection Activities ML0404104922004-02-20020 February 2004 Order EA-03-009 Service List ML0802806032003-12-12012 December 2003 NRC Question, Regarding Amag Common Header Installation ML0325214292003-08-20020 August 2003 Westinghouse - Nuclear Safety Advisory Letter NSAL-03-6, High Net Heat Input, Dated 08/20/2003 ML0802504882002-09-13013 September 2002 Apparent Cause Evaluation Content 2023-02-01
[Table view] |
Text
ADAMS Accession Number: ML19087A148 Part B Items (Onsite) - NRC information Requests (March 27, 2019) - ISI Byron U 2 1) ITEM B.1 - requested documents for the following selected weld activities
- A. Welding activity completed during prior outage.
Work Order Code Class Description 01952003-01 2 (2CV8351) Install Additional Isolation Valve downstream of 2CV8350 per EC040564 B. Welding activity scheduled to occur during the current outage.
Work Order Code Class Description 01380459-01 2 2SIJ7A, CM 2SIJ7A
-3/4"- Fab/Install SI Vent in 2A Suction per EC 381903
- 2) ITEM B.2 Documents
- ISI related corrective actions AR/IR Number Description/Topic 04097807 01/27/2018 CORROSION ON 2A DG JACKET WATER COOLER CHANNEL HEAD 0 4062274 2SI8905D - LOOP 4 HOT LEG SI CHK VL V 04137953 05/15/2018 CORROSION ON SX RISER VALVE PIPING 04058120 2RC8037C BODY/BONNET INACTIVE LEAK 04059080 BORIC ACID LEAK ON 2RC8037A 04059953 ACTIVE BORIC ACID LEAK ON 2SI051 04059979 ACTIVE BODY TO BONNET LEAK ON 2SI8905D 04064624 ACTIVE LEAK ON 2CV8368B 04085285 RCS LEAK RATE EXCEEDED ACTION LEVEL 3 04085629 U-2 RCS LEAK RATE DEVIATION ACTION LEVEL II 04087635 UNIT 2 RCS LEAK RATE CALCULATION EXCEEDED PARAMETERS 04090712 RCS LEAK RATE ACTION LEVEL 2 04121830 SX LEAK ON JACKET WATER COOLER DURING SX FLUSH 04209055 UNEXPECTED ALARM
- U-2 CONTAINMENT LEAK DETECTION HIGH 04222319 RCS LEAK RATE EXCEEDED ACTION LEVEL 3 04230553 POTENTIAL INACTIVE LEAK ON 2SX03B LINE 04155764 U2 LOOSE PARTS IMPACT NOISE MULTIPLE ALARMS RECEIVED 0 1326215 BB S-10 Small Bore Class 1 Weld Actions 02704898 2SX035 - Leak
- 3) Item B.3- Documents for Components with Relevant Indications Component AR No or Letter Supporting docs 10/12/2017
- NDE - LINEAR INDICATION OBSERVED DURING EXAM Provide a copy of AR 04062252 with all corrective action assignment s (CA s). Detailed construction/fabrication drawing for affected component and associated piping drawing.
Nondestructive Exam report(s) and completed corrective actions for AR and site procedure with acceptance criteria that were applied for this issue.
10/12/2017 B2R20 M4 NDE
- LINEAR INDICATION OBSERVED DURING EXAM Provide a copy of AR 04062274 with all CAs. Detailed construction/
fabrication drawing for affected component and associated piping drawing.
Nondestructive Exam report(s) and completed corrective actions for AR and site procedure with acceptance criteria that were applied for this issue.
Unit 2 Containment Liner Corrosion- "Based on ultrasonic testing, the maximum metal loss observed on the containment liner is 0.103" at one location. This is the only location on the containment liner that has reached 40% metal loss from nominal thickness. The nominal plate thickness of the containment liner is 0.250" thick. The two pits identified in B2R20 are the only locations for Unit
-2 that exceed the ASME Code Section Xl Subsection IWE acceptance criteria of 10%. The pit at D2 Location 1 is 27.2% metal loss from nominal thickness and the pit at D2 Location 3, mentioned previously, resulted in 41.2% metal loss. Byron Letter dated January 18, 2018
- BYRON 2018
-0002 "Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (B2R20)" Provide ARs and CAs associated with these liner pits as described in your January 18, 2018 letter. Nondestructive Exam report(s) and site procedure with acceptance criteria applied to these degraded areas. Applicable calculations that support the evaluation s of each degraded areas as described in your January 18, 2018 letter.
- 4) Item B.4- Updated Schedules
- NDE and Welding Activities as identified in A.1 of Request Letter. Specifically, include the inspection priority items selected below and a current copy of the applicable procedures:
Week of 4/8/19 (M
- F) and Week of 4/15/19 (M
- F) - NDE Activities UT, (Cat R-A, R1.11.3) 3 of 7 FW welds - (e.g. FW03DA
-16/C15, 16, 19, 20, 21, 22 or 26). Procedure
- EXE PDI-UT-1 Ultrasonic Examination of Ferritic Pipe Welds in Accordance with PDI
-UT-1. UT, (Cat B-B, Item B2.40)
- SG - Stub Barrel Channel Head Weld - 2RC-01-BA/SGC-01. Procedure
- EXE-ISI-210 - Manual Ultrasonic Examination of Vessel Welds.
PT, (Cat C-B, Item C2.21)
- Feedwater Nozzle Weld
- 2RC-01-BA/SGN-02 Procedure - ER-AA-335-002 - liquid penetrant examinations
. PT, (Cat C-C, Item C3.20) - Closure Plate 2AB
-37 Weld - 2RH02AA-8/C47 Procedure ER
-AA-335-002 - liquid penetrant examinations
. Thursday- 4/11/19 Thermal Sleeve Wear Measurement/Examination
- Work order and Procedure
- LCM 16-0002. Friday & Saturday & Monday 4/12, 13 & 15 of 2019 - BMV Examination Rx Head VE- BMV -2RC02R- Reactor Head Bare Metal visual examination
-CC-729 Procedure - ER-AP-335-001 BARE METAL VISUAL EXAMINATION FOR NICKEL ALLOY MATERIALS, R6 04/15/19 - Monday (Note Sunday 4/14/19 at 1600 Start)
Weldi ng - WO 01380459 CM 2SIJ7A-3/4"- FAB/INSTALL SI VENT IN 2A SUCT PER EC 381903 and applicable welding procedures (e.g. 8-8-GTSM, or 1-1-GTSM PWHT.