E-Mailed; Byron Station, Unit 1 - Request for Information Sent 02/14/17 (Msh)| ML17047A690 |
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| Site: |
Byron  |
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| Issue date: |
02/14/2017 |
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| From: |
NRC/RGN-III |
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| To: |
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| References |
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| Download: ML17047A690 (3) |
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Text
ADAMS Accession Number ML17047A690 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 01800481-06 1MS018C -Contingency to repair internals of valve by welding and machining to support TRIM replacement 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.
- 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.
01635685-05 1AF049B, 1AF03EB-4, 1AF03EC-4 "INSTALL (2ea.) NOZZLE CHECK VALVES, (4ea.) 4-As stated in Item B.1 of request letter; and
- 1) ASME Code Section XI repair replacement plan and reconciliation for replacement components/materials.
ADAMS Accession Number ML17047A690 900# RFWN FLANGES, (2ea.) 4 90° LONG RADIUS ELBOW, 1-1/8-7 THREADED ROD, AND 1-1/8-7 HEAVEY HEX NUTS"
- 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.
- 2) ITEM B.2 of NRC information request letter-ISI related corrective actions-Provide paper copies of the following documents.
AR/IR Number Description/Topic Supporting Docs 2559653 B1R20 M4 FOREIGN OBJECT FOUND IN 1B SG SECONDARY SIDE.
Copy of AR and all CAs and applicable evaluations 2559658 B1R20 M4 FOREIGN OBJECTS FOUND IN 1C SG SECONDARY SIDE.
Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
2661989 MIN WALL THICKNESS
<87.5% OF NOM WALL FOR SX PIPING Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
2663826 MIN WALL THICKNESS
<87.5% OF NOM WALL FOR SX PIPING Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
2713844 PROGRAM HEALTH CHALLENGE FOR SG PROGRAM Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
2568391 FME TRENDING OF THE 1CB01MB FW SUCTION STRAINER Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
02547859 Service Water Piping IR 02547859 1 SX93AB-8 Copy of AR and all CAs and applicable evaluations including applicable NDE reports.
Copy of Supporting Piping Calculation 033437 02550405 Service Water Piping IR 02550405 1 SX93AA-8 Copy of AR and all CAs and applicable evaluations.
Copy of Supporting Piping Calculation 021908 02564032 Reactor Coolant Valve Bolting IR 02564032 1 RC8037B Copy of AR and all CAs and applicable evaluations.
Copy of BACC Evaluation BYR201515923 02427918 1MSO18C - 6 NPS Main Steam Power Operated Relief Copy of AR and all CAs and applicable evaluations.
ADAMS Accession Number ML17047A690 Valve - Repair of internals by welding 02431695 OSXO3A U0 Component cooling HX outlet piping -
Pinhole leakage in weld Copy of AR and all CAs and applicable evaluations including 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.