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ML100410121
Show incoming properties 
Category
Letter  and Inspection Report
AR
AR 01014280 +  and AR 00 +
ASME section
ASME Section XI +
Accession number
ML100410121  +
Agency
Illinois Emergency Management Agency +
Area
Switchyard +
Atomic Element
Boron +, Carbon +  and Lead +
CFR
10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50 Appendix B Criterion IV, Procurement Document Control +, 10 CFR 50.54#q +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +  and 10 CFR 50.47#b +
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +  and Occupational Radiation Safety +
Correspondence
WO 826129 +
Cross cutting aspect
H.4 +, H.7 +, H.8 +  and H.11 +
Docket
05000237  +, 05000249  +, 00237  +  and 00249  +
Emergency Facility
Technical Support Center +
Engineering change
EC-368360 +, EC-372200 +, EC-377036 +, EC-378040 +  and EC-371153 +
Equipment
Portal monitor +
Equipment trip
Turbine Trip +  and Reactor Trip +
Exelon procedure
MA-AA-716-012 +, LS-AA-125 +, MA-AA-716-008 +, ER-AA-2006 +, RP-AA-220 +, LS-AA-2140 +, ER-AA-335-018 +, ER-AA-335-1008 +, RP-AA-210 +, RP-AA-203-1001 +, RP-AA-350-1001 +, MA-AA-716-230-1002 +  and RP-AA-461 +
Finding
05000237/FIN-2009005-07 +, 05000249/FIN-2009005-04 +, 05000237/FIN-2009005-04 +, 05000249/FIN-2009005-10 +, 05000237/FIN-2009005-01 +, 05000237/FIN-2009005-02 +, 05000237/FIN-2009004-04 +, 05000249/FIN-2009004-04 +, 05000237/FIN-2009005-03 +, 05000237/FIN-2009005-05 +, 05000249/FIN-2009005-06 +, 05000237/FIN-2009002-04 +, 05000249/FIN-2009005-08 +, 05000237/FIN-2009003-01 +, 05000249/FIN-2009003-01 +, 05000237/FIN-2009005-09 +, 05000249/FIN-2009005-09 +, 05000237/FIN-2009009-02 +  and 05000237/FIN-2005009-05 +
From
NRC/RGN-III/DRP/B1 +  and Ring M +
Generic letter
NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +
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ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +, ML100410121 +  and ML100410121 +
Hours
2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
IP
TI 2515/177 +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0612, Power Reactor Inspection Reports +, NRC Inspection Manual 0609/Appendix M, Significance Determination Process Using Qualitative Criteria +, IMC 0305, Operating Reactor Assessment Program +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +
Inspection procedure
IP 71111.12 +, IP 71111.04 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.19 +, IP 71114.04, Emergency Action Level and Emergency Plan Changes +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71121.02 +, IP 71121.01 +, IP 71111.05Q +, IP 71111.12Q +, IP 71111.08G +, IP 71111.20, Refueling and Other Outage Activities +, IP 71152, Problem Identification and Resolution (PI&R) +, IP 71111.04-05 +, IP 71111.05-05 +, IP 71111.12-05 +, IP 71111.13-05 +, IP 71111.15-05 +, IP 71111.19-05 +, IP 71151-05 +, IP 71152-05 +, IP 71114.04-05 +, IP 71153-05 +, IP 71111.20-05 +, IP 71111.08-05 +...
Inspection report
IR 05000237/2009005 +, IR 05000237/2009004 +, IR 05000237/2009003 +, IR 05000237/2008005 +  and IR 05000237/2009002 +
Issue date
February 10, 2010  +
Issue report
AR 01014280 +, AR 01000609 +, AR 00992912 +, AR 00911408 +, AR 00889729 +, AR 00782956 +, AR 00755744 +, AR 00711323 +, AR 00705912 +, AR 00705639 +, AR 00695137 +, AR 00691069 +, AR 00681657 +, AR 01009039 +, AR 01003797 +, AR 01005336 +, AR 01005291 +, AR 01006989 +, AR 01001725 +, AR 01002609 +, AR 01000791 +, AR 01006553 +  and AR 01007918 +
LER
05000249/LER-2009-001, Re Group I Isolation and Automatic Reactor Scram +, 05000237/LER-2009-003, Emergency Diesel Generator Oil Leak +  and 05000237/LER-2009-001, Regarding Common Mode Failure of Reactor Building Isolation Dampers +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
11:38:34, 14 January 2025  +
NRC information notice
Information Notice 97-16 +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
62  +
Person
Allan Barker +, Carole Ariano +, Linda Linn +, Steven Orth +, Tammy Tomczak +  and Jared Heck +
Power source
4kV +
Procedure
OSP +, EP-AA-1000 +, ST-MSS-352M-1 +  and ES-MS-351M-358 +
Regulatory Guide
Regulatory Guide 1.33 +
SR
SR-3.8.1 +, SR-3.1.3.3 +  and SR-4.8.1 +
SSC
D2R20-037 +, D2R21-028 +, D2R21-029 +, 07-09-294 +  and 07-09-007 +
Scram
Automatic Scram +
See also
IR 05000237/2009005 +
Site
Dresden +
Site license
DPR-19 +  and DPR-25 +
Start date
February 10, 2010  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Reactor Building Ventilation +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Low Pressure Coolant Injection +  and Emergency Feedwater System +
TS
TS-3.1.3 +, TS-3.1.5 +, TS-3.1.4 +, TS-5.4.1 +  and TS-5.4.1.a +
Title
IR 05000237-09-005, 05000249-09-005, on 10/01/09 - 12/31/09; Dresden Nuclear Power Station, Units 2 & 3; Equipment Alignment, Operability Evaluations, Post-Maintenance Testing, Surveillance Testing, Outage, and Event Follow-up  +
To
Pardee C +  and Exelon +
Topic
Safe Shutdown +, Boric Acid +, Packing leak +, High Radiation Area +, Water Inventory Control +, Enforcement Discretion +, Probabilistic Risk Assessment +, Nondestructive Examination +, Temporary Modification +, Condition Adverse to Quality +, Significance Determination Process +, Local Leak Rate Testing +, Foreign Material Exclusion +, Shift Technical Advisor +, Large early release frequency +, Stress corrosion cracking +, Loss of Offsite Power +, Commercial Grade +, Fuel cladding +, Downpower +  and Gas accumulation +
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http://pbadupws.nrc.gov/docs/ML1004/ML100410121.pdf  +
WO
WO 826129 +
Work order
WO 1286397 +, WO 548808#01 +, WO 1152490#08 +, WO 1293386 +, WO 1285845 +, WO 1098975#02 +, WO 01285845#01 +, WO 634625#01 +, WO 1077723#01 +, WO 1257282#01 +, WO 1251254#01 +, WO 1277976#01 +, WO 922770#01 +, WO 922770#02 +, WO 1079566#01 +, WO 01189798 +, WO 1186809 +, WO 1001541#76 +, WO 1294151 +, WO 1098975 +, WO 1257282 +, WO 1079209#01 +, WO 1077724#01 +, WO 1077725#01 +, WO 1081285#01 +, WO 1079266#01 +, WO 1081288#01 +  and WO 1081313#01 +
 
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