E-Mailed; Byron Station, Unit 1 - Request for Information Sent 02/14/17 (Msh)| ML17047A690 |
| Person / Time |
|---|
| Site: |
Byron  |
|---|
| Issue date: |
02/14/2017 |
|---|
| From: |
NRC/RGN-III |
|---|
| To: |
|
|---|
| References |
|---|
| Download: ML17047A690 (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
Part B Items (Onsite) - NRC Information Request (2/14/17) - IP 71111.08- Byron U1
- Documents Selected for Onsite Review.
Please provide a hard copy of the documents below to the Bryon Resident Inspectors Office on or before 10:00 am on Monday February 27, 2017.
Additionally, provide the remainder of information identified in Section B of the NRC information request letter dated December 19, 2016. Please direct questions on this request to the lead inspector Mel Holmberg at msh@nrc.gov or 630-829-9748.
- 1) ITEM B.1 - See detailed list of information needed in the NRC information request letter- Welds Selected for review- Provide paper copies of the following documents.
The following Code Class welding scheduled for the current Unit 1 outage.
Work Order Description/Topic Supporting Docs 0137025501 Replace Valve 1RH8729A As stated in Item B.1 of request letter; and
- 1) ASME Code Section XI repair replacement plan and reconciliation for replacement components/materials.
- 2) Certified Material Test Report for replacement pressure boundary materials.
The following Code Class welds completed during prior Unit 1 outage Work Order Description/Topic Supporting Docs 01800481- 1MS018C -Contingency to As stated in Item B.1 of request 06 repair internals of valve by letter; and welding and machining to 1) ASME Code Section XI repair support TRIM replacement replacement plan and reconciliation for replacement components/materials.
- 2) Certified Material Test Report for replacement pressure boundary materials.
- 3) Copies of the nondestructive examinations required by the construction Code and the pre-service examination records required by the ASME Code Section XI for the selected welds.
01635685- 1AF049B, 1AF03EB-4, As stated in Item B.1 of request 05 1AF03EC-4 letter; and
- 1) ASME Code Section XI repair "INSTALL (2ea.) NOZZLE replacement plan and CHECK VALVES, (4ea.) 4- reconciliation for replacement components/materials.
ADAMS Accession Number ML17047A690
900# RFWN FLANGES, 2) Certified Material Test (2ea.) 4 90° LONG Report for replacement pressure RADIUS ELBOW, 1-1/8-7 boundary materials.
THREADED ROD, AND 1- 3) Copies of the 1/8-7 HEAVEY HEX NUTS" nondestructive examinations required by the construction Code and the pre-service examination records required by the ASME Code Section XI for the selected welds.
- 2) ITEM B.2 of NRC information request letter- ISI related corrective actions-Provide paper copies of the following documents.
AR/IR Description/Topic Supporting Docs Number 2559653 B1R20 M4 FOREIGN Copy of AR and all CAs and OBJECT FOUND IN 1B SG applicable evaluations SECONDARY SIDE.
2559658 B1R20 M4 FOREIGN Copy of AR and all CAs and OBJECTS FOUND IN 1C SG applicable evaluations including SECONDARY SIDE. applicable NDE reports.
2661989 MIN WALL THICKNESS Copy of AR and all CAs and
<87.5% OF NOM WALL FOR applicable evaluations including SX PIPING applicable NDE reports.
2663826 MIN WALL THICKNESS Copy of AR and all CAs and
<87.5% OF NOM WALL FOR applicable evaluations including SX PIPING applicable NDE reports.
2713844 PROGRAM HEALTH Copy of AR and all CAs and CHALLENGE FOR SG applicable evaluations including PROGRAM applicable NDE reports.
2568391 FME TRENDING OF THE Copy of AR and all CAs and 1CB01MB FW SUCTION applicable evaluations including STRAINER applicable NDE reports.
02547859 Service Water Piping IR Copy of AR and all CAs and 02547859 applicable evaluations including 1 SX93AB-8 applicable NDE reports.
Copy of Supporting Piping Calculation 033437 02550405 Service Water Piping IR Copy of AR and all CAs and 02550405 applicable evaluations.
1 SX93AA-8 Copy of Supporting Piping Calculation 021908 02564032 Reactor Coolant Valve Copy of AR and all CAs and Bolting IR 02564032 applicable evaluations.
1 RC8037B Copy of BACC Evaluation BYR201515923 02427918 1MSO18C - 6 NPS Main Copy of AR and all CAs and Steam Power Operated Relief applicable evaluations.
ADAMS Accession Number ML17047A690
Valve - Repair of internals by welding 02431695 OSXO3A U0 Component Copy of AR and all CAs and cooling HX outlet piping - applicable evaluations including Pinhole leakage in weld applicable NDE reports.
- 3) Vendor Procedures (AREVA) for Reactor Vessel Head Penetration Examination - Provide paper copies of the following documents.
- 1. 54-ISI-460 - Multi-Frequency Eddy Current Examination of Nozzle Welds and Regions
- 2. 54-ISI-494 - Multi-Frequency Eddy Current Array Probe Examination of Vent Line and RVLIS Nozzle Bores
- 3. 54-ISI-603 - Automated Ultrasonic Examination of RPV Closure Head Penetrations Containing Thermal Sleeves
- 4. 54-ISI-604 - Automated Ultrasonic Examination of Open Tube RPV Closure Head Penetrations
- 4) Vendor Procedures (Wesdyne) for NDE - Provide paper copies of the following documents.
- 1. EXE-ISI-210 - Manual Ultrasonic Examination of Vessel Welds
- 2. EXE-PDI-UT Ultrasonic Examination of Ferritic Pipe Welds in Accordance with PDI-UT-1
- 3. EXE-PDI-UT Ultrasonic Examination of Austenitic Piping Welds in Accordance with PDI-UT-2
- 4. EXE-PDI-UT Ultrasonic Through Wall Sizing of Flaws in Pipe Welds in Accordance with PDI-UT-3
- 5. EXE-PDI-UT Straight Beam Ultrasonic Examination of Bolts and Studs in Accordance with PDI-UT-5
- 6. EXE-PDI-UT-108 - Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Welds in Accordance with PDI-UT-8
- 7. EXE-UT Ultrasonic Examination of Unit 1 Replacement Steam Generator Primary Manway Studs at Byron and Braidwood
- 8. EXE-UT-350 - Procedure for Acquiring Material Thickness and Weld Contours
- 9. WDI-SSP-1194 - Ultrasonic Examination of Reactor Pressure Vessel Welds in Accordance with PDI-UT-6
- 10. WDI-SSP-1292 - Manual Ultrasonic Though Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds in Accordance with PDI-UT-7.
- 11. Latest approved PDI generic procedures used as basis for the vendor/site procedures that will be used to perform UT examination of welds during the outage.
- 12. EPRI - PDQS that support each of the PDI procedures identified in item 11 above.
- 5) Schedule for bare metal visual examination of the Unit 1 reactor vessel head and site point of contact for this activity.
ADAMS Accession Number ML17047A690