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ML071640334
Show incoming properties 
Category
Letter, Technical Specification  and Bases Change
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML071640334  +
Atomic Element
Boron +, Iodine +, Nitrogen +, Xenon +, Lead +, Samarium +  and Erbium +
CFR
10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.36#c2ii +  and 10 CFR 50.71#e +
Docket
05000361  +, 05000362  +, 00361  +  and 00362  +
Equipment trip
Reactor Trip +
From
Southern California Edison +  and Scherer A +
General design criterion
GDC 15 +, GDC 10 +, GDC 14 +, GDC 30 +, GDC 28 +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +
Generic letter
NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +  and NRC Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation +
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>.
ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +, ML071640334 +  and ML071640334 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 0.00139 d (0.0333 hours, 1.984127e-4 weeks, 4.566e-5 months)  +  and 9.722222e-4 d (0.0233 hours, 1.388889e-4 weeks, 3.1962e-5 months)  +
IEEE
IEEE 279 +
Issue date
June 11, 2007  +
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>.
04:16:23, 15 January 2025  +
NEI
NEI 97-06, Steam Generator Conditioning Monitoring Report +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-1366, Amends 170 & 152 to Licenses NPF-9 & NPF-17,respectively, Incorporating Guidance & Recommendations for Diesel Generators Contained in NUREG-1366,GL 93-05,Gl 94-01 & NUREG-1431 +
Page count
161  +
Power source
4kV +
Procedure
ES +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.177 +, Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.93 +  and Regulatory Guide 1.121 +
SR
SR-3.1.5.3 +, SR-3.8.1.1 +, SR-3.4.13.1 +, SR-3.4.3.1 +, SR-3.6.3.4 +, SR-3.0.4 +, SR-3.1.1.2 +, SR-3.1.2.1 +, SR-3.6.3.3 +, SR-3.1.1.1 +, SR-3.1.6.1 +, SR-3.1.7.1 +, SR-3.6.3.1 +, SR-3.6.3.2 +, SR-3.4.6.2 +, SR-3.4.13.2 +, SR-3.4.17.1 +, SR-3.4.17.2 +, SR-3.4.3.2 +, SR-3.3.11.5 +, SR-3.3.11.4 +, SR-3.4.12.2.1 +, SR-3.4.12.2.2 +, SR-3.4.12.1.1 +, SR-3.4.12.1.2 +, SR-3.4.12.1.3 +, SR-3.4.12.1.4 +, SR-3.4.12.1.5 +, SR-3.4.12.1.6 +, SR-3.4.3.1.1 +...
SSC
2q-7 +, 4I-6 +, 3HV-6212 +, 3HV-6213 +, 3HV-6218 +  and 3HV-6219 +
Site
San Onofre +
Start date
June 11, 2007  +
State
Washington +  and California +
System
Steam Generator +, Reactor Coolant System +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +  and Containment Spray +
TS
TS-3.4.14 +, TS-3.0.3 +, TS-3.4.13 +, TS-3.5.2 +, TS-3.5.3 +, TS-3.4.5 +, TS-3.8.2 +, TS-3.4.16 +, TS-3.7.10 +, TS-3.4.4 +, TS-3.4.8 +, TS-3.4.12 +, TS-3.4.3 +, TS-3.3.2 +, TS-3.1.7 +, TS-3.1.6 +, TS-3.4.10 +, TS-3.1.2 +, TS-3.4.6 +, TS-3.8.9 +, TS-3.4.7 +, TS-3.1.5 +, TS-3.1.1 +, TS-3.4.15 +, TS-3.9.5 +, TS-3.9.4 +, TS-3.9.1 +, TS-3.4.17 +, TS-3.2.4 +, TS-3.2.1 +...
Title
Cycle Specific Technical Specification Bases Page Updates  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Boric Acid +, Shutdown Margin +, High Radiation Area +, Non-Destructive Examination +, Anticipated operational occurrence +, Time to boil +, Hydrostatic +, Probabilistic Risk Assessment +, Stress corrosion cracking +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Offsite Circuit +, Unidentified leakage +, Operational leakage +, Thermal fatigue +  and Pressure Temperature Limits Report +
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http://pbadupws.nrc.gov/docs/ML0716/ML071640334.pdf  +
 
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