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IR 05000327/2009003
Show incoming properties 
Category
Letter  and Inspection Report
ASME section
ASME Section XI +
Accession number
ML092040406  +
Atomic Element
Boron +, Carbon +  and Lead +
CFR
10 CFR 20 +, 10 CFR 2.390 +, 10 CFR 19.12 +, 10 CFR 50.9 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.55a +, 10 CFR 50.73#a2iB +, 10 CFR 50.73#a2ivA +, 10 CFR 50.73#a2vD +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a +, 10 CFR 50.75#g +  and 10 CFR 20.2206#c +
CY
CY 2008 +
Code case
ASME Code Case N-729-1 +  and ASME Code Case N-722 +
Contact
R. Bernhard +, T. Cleary +, Siva Lingam +, D. Bodine +, M. Halter +, P. Simmons +, C. Church +, R. Thompson +, T. Marshall +, S. McCamy +, B. Wetzel +, K. Wilkes +, M. Kerwin +, J. Dvorak +, D. Clift +, N. Eggemeyer +, D. Boone +, L. Cross +, G. Morris +, S. Holdeffer +  and Kenneth Jones +
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +
Correspondence
CY 2008 +
Docket
05000327  +, 05000328  +, 00327  +  and 00328  +
ENS
ENS 45029 +, ENS 45045 +, ENS 45085 +  and ENS 45097 +
EPRI MRP
MRP-139 +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +  and Reactor Trip +
FOIA
FOIA/PA-2010-0209 +
Finding
05000327/FIN-2009003-02 +
From
Eugene Guthrie +  and Reactor Projects Region 2 Branch 6 +
General design criterion
GDC 19, Control room +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +
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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Hours
6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +
IP
TI 2515/172 +
IP sample
IP 71111.08P +
Inspection Manual Chapter
NRC Inspection Manual 0609 +, NRC Inspection Manual 0609/Appendix A +  and IMC 0305, Operating Reactor Assessment Program +
Inspection procedure
IP 71151 +, IP 71122.02 +, IP 71121.02 +, IP 71121.01 +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000327/2009003 +
Isotope
Tritium +
Issue date
July 23, 2009  +
LER
05000327/LER-2008-002, Loss of a Main Control Air Handling Unit in Conjunction with an Emergency Power Source Out of Service +
License amendment topic
Alternate Source Term +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Foxboro +
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>.
15:52:39, 14 January 2025  +
NEI
NEI 99-02, Regulatory Assessment Performance Indicator Guideline +
NUREG
NUREG-1608 +, NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  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 +
Page count
47  +
Procedure
AOP +, Emergency Operating Procedure +  and AOP-M.04 +
Regulatory Guide
Regulatory Guide 1.33 +, Regulatory Guide 8.8 +  and Regulatory Guide 8.13 +
Report number
3  +
SSC
1B-B +  and 1A-A +
Scram
Manual Scram +  and Automatic Scram +
Site
Sequoyah +
Site license
Sequoyah +
Start date
July 23, 2009  +
State
Tennessee +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Turbine +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Moisture Separator Reheater +, Control Rod +  and Extraction steam +
TS
TS-3.0.5 +, TS-3.9.4 +, TS-6.8.1.a +  and TS-6.8 +
Title
IR 05000327-09-003 and 05000328-09-003, on 04/01/2009 - 06/30/2009; Sequoyah Nuclear Plant, Units 1 and 2; Event Followup  +
To
Tennessee Valley Authority +  and Swafford P +
Topic
Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Weld Overlay +, Enforcement Discretion +, VT-2 +, Locked High Radiation Area +, Significance Determination Process +, Foreign Material Exclusion +, Flow Accelerated Corrosion +, Feedwater Heater +, Process Control Program +, Eddy Current Testing +, DM weld +, Power change +, Unidentified leakage +, Manual Operator Action +  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/ML0920/ML092040406.pdf  +
Year
2,009  +
 
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