Browse wiki

Jump to navigation Jump to search
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +
ANSI code
ANSI B31.1 +, ANSI N14.6 +  and ANSI B30.2-1976 +
ASME section
ASME Section III +  and ASME Section VIII +
Accession number
ML15279A269  +
Atomic Element
Boron +, Iodine +, Nitrogen +, Sodium +, Hydrogen +, Lead +  and Tin +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 2 +, 10 CFR 50.49 +  and 10 CFR 50.55a#f +
Code case
ASME Code Case N-411 +, ASME Code Case N-318 +, ASME Code Case N-318-3 +  and ASME Code Case N-122 +
Correspondence
ND-3500 +
Docket
05000391  +, 00412  +, 00507  +, 00508  +, 00509  +, 00524  +, 00525  +, 00549  +, 00562  +  and 00563  +
Equipment trip
Reactor Trip +
From
Tennessee Valley Authority +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 81-07, Control of Heavy Loads +  and NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +
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>.
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +, NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +  and NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6 +
Hours
0.00278 d (0.0667 hours, 3.968254e-4 weeks, 9.132e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
IEEE
IEEE 344 +, IEEE 382 +, IEEE 344-1975 +, IEEE 323-1971 +  and IEEE 344-1971 +
In package
ML15279A332 +
Isotope
Tritium +
Issue date
September 11, 2015  +
Manufacturer
Westinghouse +, Foxboro +  and Ametek +
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>.
08:09:22, 13 July 2018  +
ND
ND-3500 +
NEI
NEI 08-05 +
NFPA
NFPA 30 +, NFPA 13 +, NFPA 14 +, NFPA 15 +  and NFPA 24 +
NRC bulletin
NRC Bulletin 88-11 +
NUREG
NUREG/CR-0200 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +  and NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +
Page count
282  +
Power source
600V +
Procedure
ST +, SAP +, RT +  and SP-58 +
Project reference
TAC:M85802 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.4 +, Regulatory Guide 1.84 +, Regulatory Guide 1.61 +, Regulatory Guide 1.68 +, Regulatory Guide 1.20 +, Regulatory Guide 1.48 +, Regulatory Guide 1.67 +  and Regulatory Guide 1.73 +
SSC
1B-B +, 2B-B +, 1A-A +, 2A-A +, 3DCU-9 +, 07-63-561 +, 07-63-559 +, 07-63-633 +, 07-63-635 +, 07-63-563 +, 07-63-623 +, 07-63-625 +, 07-63-641 +, 07-63-644 +, 07-68-564 +, 07-63-549 +, 07-52-505 +, 07-74-514 +, 1CKV-62-561 +, 1CKV-62-563 +, 3CKV-63-510 +, 3RFV-63-534 +, 3RFV-63-536 +, 4RFV-63-602 +, 3RFV-63-604 +, 3RFV-63-626 +, 3RFV-63-637 +, 4Self-actuate +, 47W801-2BBFCV-1-7 +, 47W803-2BBFCV-1-15 +...
Site
Watts Bar +
Start date
September 11, 2015  +
State
Ohio +, Tennessee +, Georgia +, Washington +  and California +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Shield Building +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +
Title
Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Operating Basis Earthquake +, Emergency Lighting +, Finite Element Analysis +, High Energy Line Break +, Tornado-Generated Missile +, Design basis earthquake +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Through-Wall Leakage +, Flow Induced Vibration +, Overspeed trip +, Water hammer +  and Leak-Before-Break +
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/ML1527/ML15279A269.pdf  +
WCAP
WCAP-8687 +, WCAP-7817 +, WCAP-8673 +, WCAP-8373 +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-8929 +, WCAP-8252 +, WCAP-5890 +, WCAP-7769 +, WCAP-8587 +, WCAP-8317-A +, WCAP-8517 +, WCAP-8709-A +, WCAP-8708-PA +, WCAP-15102 +, WCAP-8830 +, WCAP-9735 +, WCAP-15245 +, WCAP-7918 +, WCAP-8831 +, WCAP-7879 +, WCAP-11522 +, WCAP-15699 +, WCAP-11627 +, WCAP-8674 +  and WCAP-10448 +
Westinghouse report
WCAP-8687 +, WCAP-7817 +, WCAP-8673 +, WCAP-8373 +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-8929 +, WCAP-8252 +, WCAP-5890 +, WCAP-7769 +, WCAP-8587 +, WCAP-8317-A +, WCAP-8517 +, WCAP-8709-A +, WCAP-8708-PA +, WCAP-15102 +, WCAP-8830 +, WCAP-9735 +, WCAP-15245 +, WCAP-7918 +, WCAP-8831 +, WCAP-7879 +, WCAP-11522 +, WCAP-15699 +, WCAP-11627 +, WCAP-8674 +  and WCAP-10448 +
 
Retrieved from "https://kanterella.com/Special:Browse/:NL-2D15-2D183,-20Watts-20Bar-20Nuclear-20Plant,-20Unit-202,-20Amendment-20114-20to-20Final-20Safety-20Analysis-20Report,-20Section-203.0-20-2D-20Design-20of-20Structures,-20Components,-20Equipment,-20and-20Systems,-20Pages-203.8.5-2D1-20-2D-203.12-2D6"