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ML073340491
Show incoming properties
Category
Audit Report
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML073340491  +
Atomic Element
Boron +, Nickel +  and Hydrogen +
CFR
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 5 Appendix J +  and 10 CFR 54.21#d +
Contact
Wen P, NRR/DLR/RLRC, 415-2832 +
Correspondence
WM-89-0015 +, WO 04-0039, 60-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. +, WM 04-0004, Response to NRC Order, Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 04-0002, 60-Day Report for NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity. +, WM 04-0001, Report for NRC Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity +, PM 29101 +, PM 35992 +  and WM 06-0051, Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +
Docket
05000482  +  and 00482  +
Document
ML030380470 +, ML040220181 +, ML070230166 +  and ML052640091 +
Drawing
FP-452 +, FP-209 +, FP-211 +, FP-600 +, FP-225 +, FP-400 +  and FP-440 +
From
NRC/NRR/ADRO/DLR +
Generic letter
NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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>.
ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +, ML073340491 +  and ML073340491 +
In package
ML073300543 +
Issue date
February 14, 2008  +
License amendment topic
License Renewal Application +
Manufacturer
Westinghouse +
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>.
00:45:20, 15 January 2025  +
NEI
NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +
NRC bulletin
NRC Bulletin 04-01 +, NRC Bulletin 02-01 +  and NRC Bulletin 03-02 +
NUREG
NUREG-1431 +, NUREG/CR-6260 +, NUREG-1901 +, NUREG-1787, Safety Evaluation Report Related to the License Renewal of the Virgil C. Summer Nuclear Station +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
PM
PM 29101 +  and PM 35992 +
Page count
28  +
Person
Zhian Li +, Dan Hoang +, Duc Nguyen +  and Veronica Rodriguez +
Procedure
RT +  and CH-015 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML073340491 +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.137 +  and Regulatory Guide 1.127 +
SSC
16F-001 +, 07-28-011 +, 05G-004 +, 05G-002 +, 23M-001 +, 29E-001 +, 23M-007 +, 29A-002 +, 29A-005 +, 16A-003 +, 16F-002 +, 28A-001 +, 29D-001 +, 23L-002 +, 23L-001 +, 23H-002 +, 29A-27 +, 07A-008 +, C151Q-01 +, 07-28-007 +, 23M-020 +  and 05G-01 +
Site
Wolf Creek +
Site license
NPF-42 +
Start date
February 14, 2008  +
State
Kansas +  and Pennsylvania +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, HVAC +, Reactor Pressure Vessel +, Fuel Pool Cooling and Cleanup +  and Containment Spray +
Title
Audit Summary Regarding the License Renewal for the Wolf Creek Generation Station  +
Topic
Boric Acid +, Fire Barrier +, Hydrostatic +, Aging Management +, Flow Accelerated Corrosion +, Integrated leak rate test +, Eddy Current Testing +, License Renewal +, Maintenance Rule Program +, Fire Protection Program +  and Thermography +
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/ML0733/ML073340491.pdf  +
Vendor
Framatome +
WCAP
WCAP-12866 +  and WCAP-14173 +
WM
WM-89-0015 +, WM 04-0004, Response to NRC Order, Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 04-0002, 60-Day Report for NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity. +, WM 04-0001, Report for NRC Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +, WM 03-0044, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations & Reactor Coolant Pressure Boundary Integrity +  and WM 06-0051, Day Report for NRC Order EA-03-009, Issuance of First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors +
WO
WO 04-0039, 60-Day Response to NRC Bulletin 2004-01, 'Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors. +
Westinghouse report
WCAP-12866 +  and WCAP-14173 +
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