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ML17206A059
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ACI
ACI-318 +
ANSI code
ANSI B31.1 +, ANSI N18.2 +, ANSI B16.5 +, ANSI B31.7 +, ANSI B31.1.0 +, ANSI B16.11 +, ANSI B31.1-1967 +, ANSI 18.2 +, ANSI B31.1-1973 +, ANSI B31.7-1969 +, ANSI/ANS 58.2-1980 +, ANSI B31.7- 1969 +, ANSI B31.1- 1967 +  and ANSI/ANS-58.2-1980 +
ASME code
IWA-4000 +  and IWA-7000 +
ASME section
ASME Section XI +, ASME Section III +, ASME Section I +, ASME Section V +  and ASME Section VIII +
Accession number
ML17206A059  +
Agency
Occupational Safety and Health Administration +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Iron +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Radon +, Chloride +, Lead +, Helium +, Aluminum +, Argon +  and Manganese +
CFR
10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.49 +, 10 CFR 100 Appendix A +, 10 CFR 50 Appendix B Criterion III, Design Control +, 10 CFR 50.55a +, 10 CFR 50.49#b +, 10 CFR 50.49#b1 +, 10 CFR 50.49#l +, 10 CFR 50.49#k +, 10 CFR 50.55a#f +, 10 CFR 50.55a#2 +, 10 CFR 50.55a#f4 +  and 10 CFR 50.55#a +
CR
LO-LAR-88-00008 +
Code case
ASME Code Case N-411 +  and ASME Code Case N-318 +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Emergency Preparedness +, Barrier Integrity +  and Mitigating Systems +
Correspondence
DCL-91-026 +, DCL-92-084 +, DCL-91-178 +, DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +, DCL-92-198 +, DCL-94-133 +, DCL-86-009 +, DCL-87-070 +, DCL-90-289 +, DCL-88-288 +, DCL-87-082, Applicant Exhibit A-7,consisting of Forwarding Three-Dimensional Studies of High Density Spent Fuel Racks (Acorn 10 & Acorn 12), in Response to NRC 870401 Request for Addl Info Re Spent Fuel Rack Integrity +, DCL-84-088, Responds to NRC Re Violations Noted in IE Insp Rept 50-275/83-40.Corrective actions:831227 Interofc Memo Issued to All Engineering Disciplines Covering Procedures to Revise Existing Files & Prepare New Files +, PM-80 +  and DCL-92-059, Forwards Nonproprietary WCAP-13038 & Proprietary WCAP-13039, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis For.... Proprietary WCAP-13039 Withheld (Ref 10CFR2.790) +
Cross cutting aspect
S.6(f) +
DCL
DCL-91-026 +, DCL-92-084 +, DCL-91-178 +, DCL-17-038, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 8, Electric Power +, DCL-92-198 +, DCL-94-133 +, DCL-86-009 +, DCL-87-070 +, DCL-90-289 +, DCL-88-288 +, DCL-87-082, Applicant Exhibit A-7,consisting of Forwarding Three-Dimensional Studies of High Density Spent Fuel Racks (Acorn 10 & Acorn 12), in Response to NRC 870401 Request for Addl Info Re Spent Fuel Rack Integrity +, DCL-84-088, Responds to NRC Re Violations Noted in IE Insp Rept 50-275/83-40.Corrective actions:831227 Interofc Memo Issued to All Engineering Disciplines Covering Procedures to Revise Existing Files & Prepare New Files +  and DCL-92-059, Forwards Nonproprietary WCAP-13038 & Proprietary WCAP-13039, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis For.... Proprietary WCAP-13039 Withheld (Ref 10CFR2.790) +
Docket
05000275  +, 05000323  +, 00275  +  and 00323  +
Drawing
FP-0-307 +, FC-1 +, Drawing 3.2-17 +, Drawing 3.5-17 +, Drawing 3.6-30 +, Drawing 3.8-98 +, LP-Rotor +, FP-0-306 +, FB-29 +, FE-5001 +, FE-5014 +, FC-2 +, FC-3 +  and FC-4 +
Effective date
February 22, 1983  +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Pacific Gas & Electric +
Fuel cladding
ZIRLO +
General design criterion
GDC 33 +, GDC 57 +, GDC 20 +, GDC 49 +, GDC 50 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 56 +, GDC 18 +, GDC 11 +, GDC 30 +, GDC 31 +, GDC 39 +, GDC 45 +, GDC 40 +, GDC 25 +, GDC 6 +, GDC 28 +, GDC 62 +, GDC 22 +, GDC 29 +, GDC 37 +, GDC 42 +, GDC 8 +, GDC 7 +, GDC 9 +, GDC 27 +, GDC 32 +...
Generic letter
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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>.
ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +, ML17206A059 +  and ML17206A059 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00278 d (0.0667 hours, 3.968254e-4 weeks, 9.132e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
IEEE
IEEE 344-1987 +, IEEE 344 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 344-1975 +, IEEE 323-1971 +, IEEE 344-1971 +, IEEE 535 +, IEEE 535-1979 +  and IEEE 535-1986 +
In package
ML17206A046 +
Issue date
December 31, 2016  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Cutler-Hammer +, Westinghouse +, Allen-Bradley +, Honeywell +, Limitorque +, Valcor +, General Electric +, Nuclear Measurements +  and Johnson Controls +
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>.
23:19:16, 18 May 2018  +
NEI
NEI 97-04 +
NFPA
NFPA 805 +
NRC bulletin
NRC Bulletin 80-11 +
NUMARC
NUMARC 87-00 +
NUREG
NUREG/CR-1780 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0675, Forwards Decision DD-86-12 in Response to Petition & Suppls Re Licensing Actions Based on Allegations.Nrc Evaluation of Allegation & Basis for Conclusions in Decision DD-86-12 Contained in Sser 33 to NUREG-0675,transmitted on 860527 +, 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 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +
PM
PM-80 +
Page count
1,004  +
Power source
4.16kV +
Procedure
MST +, AM +, RAP +, ST +, SAP +, SP +, CP +, Emergency Operating Procedure +, CP-38 +, CP-35 +, CP-36 +, ES-68-1 +, ES-66 +, ES-15-1 +  and CP-37 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML17206A059 +
Project reference
TAC:MA1152 +, TAC:M68537 +  and TAC:M83614 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +, Regulatory Guide 1.180 +, Regulatory Guide 1.63 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.100 +, Regulatory Guide 1.26 +, Regulatory Guide 1.29 +, Regulatory Guide 1.55 +, Regulatory Guide 1.61 +, Regulatory Guide 1.13 +, Regulatory Guide 1.89 +, Regulatory Guide 1.115 +, Regulatory Guide 1.15 +, Regulatory Guide 1.46 +  and Regulatory Guide 1.158 +
SSC
2E-2 +, 2E-5 +, 2E-6 +, 2E-4 +, 2E-1 +, T26S-18 +, 2S-2 +, 2S-1 +, 531R-1979 +, 33A-E +, 35A-E +, 35A-C +, 3AA-2265 +, 3AA-3500 +, 3AA-2015 +, 2S-67 +, 2S-68 +, 2S-69 +, 2FD-4 +, 2FD-5 +, 2FD-6 +, 2EFC-1 +, 2EFC-5 +, 2EFC-6 +, 2EFH-1 +, 2EFH-2a +, 2EFH-2b +, 2EFH-4 +, 2EFH-5 +, 2EFH-6 +...
Scram
Automatic Scram +
Site
Diablo Canyon +
Site license
DPR-76 +  and Diablo Canyon +
Start date
December 31, 2016  +
State
Connecticut +, Illinois +, Washington +, California +, Alabama +, New York +  and Michigan +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, Main Turbine +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Electrohydraulic Control +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Extraction steam +
TS
TS-3.7.11 +
Title
Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 3, Design of Structures, Components, Equipment, and Systems  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Fitness for Duty +, High winds +, Shutdown Margin +, Loop seal +, Ultimate heat sink +, Stroke time +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Emergency Lighting +, Incorporated by reference +, Finite Element Analysis +, High Energy Line Break +, Tornado-Generated Missile +, Tornado Generated Missile +, Tornado Missile Protection +, Design basis earthquake +, Notice of Violation +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Code Reconciliation +, Earthquake +...
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http://pbadupws.nrc.gov/docs/ML1720/ML17206A059.pdf  +
WCAP
WCAP-15029 +, WCAP-8687 +, WCAP-15029-P-A +, WCAP-15030-NP-A +, WCAP-8624 +, WCAP-11525 +, WCAP-8929 +, WCAP-8172-A +, WCAP-8708-P-A +, WCAP-8709-A +, WCAP-9346 +, WCAP-8082 +, WCAP-7950 +, WCAP-7422 +, WCAP-8830 +, WCAP-8708 +, WCAP-7113 +, WCAP-7756 +, WCAP-13039 +, WCAP-9735 +, WCAP-9241 +, WCAP-8821 +, WCAP-16054 +, WCAP-8021 +, WCAP-8694 +, WCAP-8921 +, WCAP-8941 +, WCAP-10358 +, WCAP-10359 +, WCAP-12714 +...
Westinghouse report
WCAP-15029 +, WCAP-8687 +, WCAP-15029-P-A +, WCAP-15030-NP-A +, WCAP-8624 +, WCAP-11525 +, WCAP-8929 +, WCAP-8172-A +, WCAP-8708-P-A +, WCAP-8709-A +, WCAP-9346 +, WCAP-8082 +, WCAP-7950 +, WCAP-7422 +, WCAP-8830 +, WCAP-8708 +, WCAP-7113 +, WCAP-7756 +, WCAP-13039 +, WCAP-9735 +, WCAP-9241 +, WCAP-8821 +, WCAP-16054 +, WCAP-8021 +, WCAP-8694 +, WCAP-8921 +, WCAP-8941 +, WCAP-10358 +, WCAP-10359 +, WCAP-12714 +...
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