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ML15329A157
Show incoming properties 
Category
Letter  and Inspection Report
Accession number
ML15329A157  +
Atomic Element
Oxygen +  and Carbon +
CFR
10 CFR 21 +, 10 CFR 50 Appendix B +  and 10 CFR 50 Appendix B Criterion V +
Cornerstone
Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Correspondence
L-48011 +, PM-018-0345 +  and PM-018-0366 +
Docket
05000354  +  and 00354  +
Document
ML15329A157 +
Equipment trip
Reactor Trip +
Exelon procedure
OP-AA-108-115 +, MA-AA-723-300 +, LS-AA-125 +, LS-AA-120 +, MA-AA-723-301 +, MA-AA-716-210-1001 +, CC-AA-11 +, ER-AA-302-1008 +, OU-AA-335-016 +, ER-AA-300 +, ER-AA-302-1003 +, MA-AA-723-300-1005 +, MA-AA-724-113 +, OP-AA-108-115-1001 +  and OP-AA-111-1001 +
Finding
05000354/FIN-2015007-01 +  and 05000354/FIN-2015007-02 +
From
Paul Krohn +  and Engineering Region 1 Branch 2 +
Generic letter
NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +
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ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +, ML15329A157 +  and ML15329A157 +
Inspection Manual Chapter
NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +  and IMC 0310, Aspects within the Cross-Cutting Areas +
Inspection procedure
IP 71111.21 +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000354/2015007 +  and IR 05000254/2015007 +
Issue date
November 25, 2015  +
Issue report
AR 02015007 +
L
L-48011 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Cutler-Hammer +, Westinghouse +, Limitorque +  and 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>.
11:22:04, 10 January 2025  +
NRC information notice
Information Notice 92-26 +, Information Notice 93-98 +, Information Notice 2013-17, Significant Plant Transient Induced by Safety-Related Direct Current Bus Maintenance at Power +, Information Notice 2013-14, Potential Design Deficiency in Motor-Operated Valve Control Circuitry +, Information Notice 2013-05, Battery Expected Life and Its Potential Impact on Surveillance Requirements +, Information Notice 2012-03, Design Vulnerability in Electric Power System +, Information Notice 2011-12, Reactor Trips Resulting from Water Intrusion Into Electrical Equipment +, Information Notice 2010-03, Failures of Motor-Operated Valves Due to Degraded Stem Lubricant +  and Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +
PM
PM-018-0345 +  and PM-018-0366 +
Page count
42  +
Power source
4.16KV +  and 4kV +
Procedure
ST +  and Emergency Operating Procedure +
Regulatory Guide
Regulatory Guide 1.97 +
SSC
1GSHV-4964 +, 1GSHV-11541 +, 1EA-HV-2198 +, 1EAHV-2198C +, 1EAHV-2198 +, 1C-F-509 +, 1D-F-509 +, 1BC-HV-F021 +, 1FD-HV-F001 +, H1KB-10-K-100 +, 1BCHV-F021B +, H1SB-1SBTY-3881 +, 1EGHV-2457 +, 1EGHV-2520 +, H1GS-1GSPSV-5030 +, 1FDHV-F001 +, H1BC-BC-HV +, H1EA-EA-HV-219 +, 4HT-14-028 +, 1KBFSH-7618 +, E21A-K22A +, E21A-K22B +, E21A-K22C +, E21A-K22D +, H1BJ-1BJLT-4805-1 +, 10SA-A092 +, 1EAV-474 +  and 34APKD-4 +
See also
IR 05000354/2015007 +
Site
Hope Creek +
Site license
Hope Creek +
Start date
November 25, 2015  +
State
Washington +
System
Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +  and Main Steam +
Title
IR 05000354/2015007; 9/21/15 to 10/23/15; Hope Creek Generating Station; Component Design Bases Inspection  +
To
PSEG +  and Braun R +
Topic
Unanalyzed Condition +, Post Accident Monitoring +, Probabilistic Risk Assessment +, Coatings +, Anchor Darling +, Functionality Assessment +, Finite Element Analysis +, Significance Determination Process +, Surveillance Frequency Control Program +, Large early release frequency +, Operability Determination +, Time Critical Operator Action +, Battery sizing +, Maintenance Rule Program +, Weak link +  and Operability Assessment +
Training curricula
J-11-0-9 +
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http://pbadupws.nrc.gov/docs/ML1532/ML15329A157.pdf  +
 
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