Browse wiki

Jump to navigation Jump to search
JPN-88-041
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI B31.1 +
ASME code
IWB-3640 +, IWB-3641 +  and IWB-3500 +
ASME section
ASME Section XI +
Accession number
ML20151X102  +
Atomic Element
Copper +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Magnesium +, Chromium +, Tin +  and Tungsten +
Correspondence
JPN-88-41 +, JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl +, JPN-87-008, Forwards Technical Justification for Continued Operation of Ja Fitzpatrick Nuclear Power Plant W/Existing Recirculation Sys Piping. Weld Overlay Repairs Meet Guidelines of Generic Ltr 84-11 & Draft NUREG-0313,Rev 2 +, JPN-87-018, Forwards Addl Info on Results of IGSCC During Reload 7/Cycle 8 Outage.Total of 48 Welds Inspected Including,Overlays & Cracked Welds.Util Plans to Implement Leakage Surveillance, Per Generic Ltr 84-11 +  and JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +
Docket
05000333  +  and 00333  +
From
Power Authority of the State of New York +  and John Brons +
Generic letter
NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 34-11 +  and NRC Generic Letter 64-11 +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +, JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +  and JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +
Hours
0.0631 d (1.513 hours, 0.00901 weeks, 0.00207 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +, 0.0463 d (1.111 hours, 0.00661 weeks, 0.00152 months)  +, 0.0694 d (1.667 hours, 0.00992 weeks, 0.00228 months)  +, 0.0347 d (0.833 hours, 0.00496 weeks, 0.00114 months)  +, 0.0579 d (1.389 hours, 0.00827 weeks, 0.0019 months)  +, 0.0047 d (0.113 hours, 6.712963e-4 weeks, 1.54483e-4 months)  +, 6.597222e-4 d (0.0158 hours, 9.424603e-5 weeks, 2.16885e-5 months)  +  and 0.0116 d (0.278 hours, 0.00165 weeks, 3.805e-4 months)  +
Issue date
August 16, 1988  +
JPN
JPN-88-41 +, JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl +, JPN-87-008, Forwards Technical Justification for Continued Operation of Ja Fitzpatrick Nuclear Power Plant W/Existing Recirculation Sys Piping. Weld Overlay Repairs Meet Guidelines of Generic Ltr 84-11 & Draft NUREG-0313,Rev 2 +, JPN-87-018, Forwards Addl Info on Results of IGSCC During Reload 7/Cycle 8 Outage.Total of 48 Welds Inspected Including,Overlays & Cracked Welds.Util Plans to Implement Leakage Surveillance, Per Generic Ltr 84-11 +  and JPN-88-041, Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs +
Manufacturer
General Electric +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
09:00:48, 11 December 2024  +
NRC bulletin
NRC Bulletin 83-02 +
NUREG
NUREG/CR-4667 +, NUREG-0323 +, NUREG/CR-4082 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +
Page count
150  +
Procedure
ST +, RT +  and Emergency Plan +
Report
NEDC-30712 +
SSC
2C-53 +, 07-28-108 +  and 11UREG-0313 +
Site
FitzPatrick +
Start date
August 16, 1988  +
State
Georgia +, Washington +  and New York +
System
Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +  and Control Rod +
TS
TS-4.1.1 +
Title
Responds to Generic Ltr 88-01 Re NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.Includes Insp Plans & Mitigation Plans.Separate Submittals Will Address Resistance Heat Stress Improvement & Change to Tech Specs  +
To
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) +
Topic
Non-Destructive Examination +, Weld Overlay +, Finite Element Analysis +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Liquid penetrant +, Dissimilar Metal Weld +  and Scaffolding +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2015/ML20151X102.pdf  +
Weld alloy
ER308L +
Retrieved from "https://kanterella.com/Special:Browse/:JPN-2D88-2D041"