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ML070950200
Show incoming properties 
Category
Report  and Technical
ASME section
ASME Section III +
Accession number
ML070950200  +
Atomic Element
Boron +, Sodium +, Xenon +, Lead +  and Tin +
BWROG
BWROG-94078 +
CFR
10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.36 +, 10 CFR 50.62 +, 10 CFR 9.17#a4 +  and 10 CFR 2.390#b4 +
Cross cutting aspect
P.1(o) +
Docket
05000410  +  and 00410  +
Engineering change
EC-552 +  and EC-1905 +
Equipment trip
Turbine Trip +
From
General Electric Co +
GE analysis
GE-NE-187-08-1090 +
GNF letter
MFN-04-116 +
Generic letter
NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +
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>.
ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +, ML070950200 +  and ML070950200 +
Issue date
March 30, 2007  +
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>.
07:26:28, 15 January 2025  +
NRC information notice
Information Notice 2001-13, Inadequate Standby Liquid Control System Relief Valve Margin +
NUREG
NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +
Page count
125  +
Procedure
CH +, MP +, PSP +  and TOP +
Project reference
TAC:MA6481 +, TAC:MA7119 +, TAC:63425 +  and TAC:M90270 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.152 +  and Regulatory Guide 1.20 +
Regulatory Issue Summary
RIS 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specification, with Respect to Limiting Safety System Settings (LSSS) During Periodic Testing and Calibration of Instrument Channels +
Report
NEDO-32465 +, NEDO-31960 +, NEDO-20566A +, NEDE-2401 +, NEDC-31336P +, NEDO-10320 +, NEDC-32410P +, NEDE-20566P +, NEDO-20533 +, NEDE-23785P +, NEDE-24011 +, NEDE-24222 +, NEDE-32176P +, NEDC-32177P +, NEDC-32084P +, NEDE-24154P +, NEDE-23785 +, NEDE-30996P +, NEDC-32992P +, NEDO-24548 +, NEDO-21061 +, NEDE-24288 +, NEDC-32950P +, NEDC-24154P +, NEDC-31994P +, NEDC-33286P +, NEDC-3241OP +, NEDO-33286 +  and NEDE-2481 +
SSC
4U-0 +
Site
Nine Mile Point +
Start date
March 30, 2007  +
State
Vermont +
System
Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.3.1.1 +, TS-3.2.4 +  and TS-2.1 +
Title
NEDO-33286, Revision 0, Aprm/Rbm/Technical Specifications/Maximum Extended Load Line Limit Analysis (Arts/Mellla) Non-Proprietary Version  +
To
Office of Nuclear Reactor Regulation +
Topic
Safety Limit Minimum Critical Power Ratio +, Anticipated operational occurrence +, High Energy Line Break +, Feedwater Heater +, Feedwater Controller Failure +, MELLLA +, Loss of Offsite Power +, Fuel cladding +, Power change +, Coast down +, Power Uprate +, Stretch Power Uprate +  and Affidavit +
Transient
Turbine bypass valve out of service +
Trip
Turbine Control Valve Fast Closure +
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http://pbadupws.nrc.gov/docs/ML0709/ML070950200.pdf  +
 
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