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IR 05000336/2017004
Show incoming properties 
Category
Letter  and Inspection Report
ASME code
IWA-5250 +
ASME section
ASME Section XI +
Accession number
ML18032A330  +
Area
Switchyard +
Atomic Element
Lead +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q +, 10 CFR 50.54#q3 +, 10 CFR 50.54#q5 +, 10 CFR 50.65#a4 +  and 10 CFR 50.55a#g6iiD +
Code case
ASME Code Case N-722-1 +  and ASME Code Case N-729-4 +
Contact
Daniel Schroeder +, M. Hall +, J. Langan +, R. Hanson +, C. Walsh +, K. Underwood +, J. Daugherty +, C. Olsen +, L. Armstrong +, D. Blakeney +, R. Borchart +, S. Brabec +, M. Bradley +, R. Garver +, M. Goolsby +, J. Grogan +, F. Newton +, M. Sweet +, E. Treptow +, M. Wynn +, F. Cietek +, M. Cote +, K. Hacker +, D. Rowe +, J. Stafford +, N. Yonker +, J. Birch +, H. McKenney +, C. Chatman +, D. Stoddard +...
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +
Docket
05000336  +, 05000423  +, 00336  +  and 00423  +
Document
ML17319A089 +
ENS
ENS 52501 +
EPRI MRP
MRP-146 +
Exelon procedure
OP-AA-100 +, OP-AA-106 +  and OP-AA-200 +
Finding
05000423/FIN-2017004-01 +
From
Daniel Schroeder +  and Reactor Projects Region 1 Branch 2 +
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>.
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IP sample
IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, IP 71111.11B +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71124.01, Radiological Hazard Assessment and Exposure Controls +, IP 71111.05A +, IP 71111.04S +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.08P +, IP 71111.11A +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, IMC 0309, Reactive Inspection Decision Basis for Reactors +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609, Appendix I +  and IMC 0310, Aspects within the Cross-Cutting Areas +
Inspection procedure
IP 71111.11B +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.11Q +, IP 71111.11A +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000336/2017004 +
Isotope
Tritium +
Issue date
February 1, 2018  +
Issue report
AR 02017004 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
07:24:20, 7 January 2025  +
NEI
NEI 99-02, Regulatory Assessment Performance Indicator Guideline +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +
Operating procedure
OP-200.11 +
Page count
57  +
Power source
4.16kV +
Procedure
CH +
Regulatory Guide
Regulatory Guide 8.38 +
Report number
4  +
SSC
3CHS-PNL01 +
Site
Millstone +
Site license
Millstone +
Start date
February 1, 2018  +
State
Connecticut +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Moisture Separator Reheater +, Main Condenser +  and Main Steam +
TS
TS-3.4.9.3 +  and TS-3.4.9.1 +
Title
Integrated Inspection Report 05000336/2017004 and 05000423/2017004  +
To
Dominion +  and Stoddard D +
Topic
Boric Acid +, High winds +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Stroke time +, Water Inventory Control +, Reserve Station Service Transformer +, Temporary Modification +, Functionality Assessment +, Significance Determination Process +, Job Performance Measure +, Local Leak Rate Testing +, Eddy Current Testing +, Operability Determination +, Downpower +, Operability Assessment +, Thermal fatigue +, Reactive Inspection +  and Gas accumulation +
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/ML1803/ML18032A330.pdf  +
Work order
WO 53103005951 +  and WO 53103065851 +
Year
2,017  +
 
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