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ML031250401
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Category
Technical Specifications
ANSI code
ANSI/ANS-56.8-1994 +
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML031250401  +
Atomic Element
Iodine +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Zirconium +  and Lead +
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 J +, 10 CFR 50.2 +, 10 CFR 50.44 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 100.11 +, 10 CFR 50.55a#c +  and 10 CFR 50.44#c3ii +
Cornerstone
Mitigating Systems +
Cross cutting aspect
H.2(f) +
Docket
05000277  +  and 05000278  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Exelon +  and Gallagher M +
General design criterion
GDC 10 +
Generic letter
NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +, NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability +  and NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +
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ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +, ML031250401 +  and ML031250401 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-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)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +
Isotope
I-131 +
Issue date
April 24, 2003  +
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>.
15:06:19, 16 January 2025  +
NEI
NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +
NRC bulletin
NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +
NUREG
NUREG/CR-3052, Amends 141 & 77 to Licenses DPR-57 & NPF-5,respectively Modifying Tech Specs to Permit Only One Recirculation Loop in Operation & to Implement Jet Pump Suveillance Recommendations of NUREG/CR-3052 +  and NUREG-0802, Safety Evaluation Accepting Revised Safety Relief Valves & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +
Page count
177  +
Power source
4kV +
Procedure
Emergency Operating Procedure +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.45 +, Regulatory Guide 1.7 +  and Regulatory Guide 1.99 +
Report
NEDO-20566A +, NEDC-32183P +, NEDC-33064P +, NEDC-32707P +, NEDC-32162P +, NEDO-22155 +, NEDC-32163P +, NEDC-32428P +  and NEDO-24229 +
SR
SR-3.6.4.1.2 +, SR-3.5.1.7 +, SR-3.5.1.4 +, SR-3.5.1.1 +, SR-3.4.4.1 +, SR-3.5.1.9 +, SR-3.5.1 +, SR-3.6.1.3 +, SR-3.5.1.6 +, SR-3.6.4.1.1 +, SR-3.6.4.1.3 +, SR-3.6.4.1.4 +, SR-3.6.4.3.2 +, SR-3.6.1.3.9 +, SR-3.5.1.8 +, SR-3.4.10.1 +, SR-3.4.3.1 +, SR-3.6.4.3.1 +, SR-3.6.1.3.8 +, SR-3.5.2.1 +, SR-3.6.1.3.1 +, SR-3.0.4 +, SR-3.6.1.1.2 +, SR-3.6.2.2.1 +, SR-3.5.3.1 +, SR-3.5.1.2 +, SR-3.4.6.1 +, SR-3.5.1.5 +, SR-3.5.2.3 +, SR-3.6.1.1.1 +...
Site
Peach Bottom +
Site license
Peach Bottom +
Start date
April 24, 2003  +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.0.3 +, TS-3.5.1 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.6.1.1 +, TS-3.5.2 +, TS-3.3.6.1 +, TS-3.6.1.6 +, TS-3.6.1.3 +, TS-3.0.4 +, TS-3.6.2.3 +, TS-3.4.5 +, TS-3.4.4 +, TS-3.4.8 +, TS-3.6.3.1 +, TS-3.4.1 +, TS-3.6.4.2 +, TS-3.3.6.2 +, TS-3.6.4.3 +, TS-3.9.7 +, TS-3.3.5.2 +, TS-3.4.7 +, TS-3.6.2.2 +, TS-3.2.2 +, TS-3.0.6 +, TS-3.6.1.2 +, TS-3.2.1 +, TS-3.1.8 +, TS-3.9.8 +, TS-3.6.1.5 +...
Test
Bench test +
Title
Submittal of Changes to TS Bases, Table of Contents Through Section B 3.6  +
To
Office of Nuclear Reactor Regulation +
Topic
Unanalyzed Condition +, Reactor Vessel Water Level +, High Radiation Area +, Grab sample +, Stroke time +, Hydrostatic +, Squib +, Abnormal operational transient +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Excess Flow Check Valve +, Fuel cladding +, Pressure Boundary Leakage +, Unidentified leakage +, Operational leakage +  and Water hammer +
Turbine component
Turbine bypass valve +
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http://pbadupws.nrc.gov/docs/ML0312/ML031250401.pdf  +
 
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