Pages that link to "NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements"
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The following pages link to NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements:
Displayed 2 items.
- NRC Generic Letter 87-11 (redirect page) (← links)
- ML17046A289 (← links)
- ML17130A273 (← links)
- ML17206A059 (← links)
- ML17039A603 (← links)
- ML16280A159 (← links)
- ML17033B500 (← links)
- ML16256A137 (← links)
- ML16256A201 (← links)
- ML16251A168 (← links)
- ML16168A348 (← links)
- ML16168A377 (← links)
- ML16180A142 (← links)
- ML16165A454 (← links)
- ML16054A440 (← links)
- Information Notice 2000-20, Potential Loss of Redundant Safety Related Equipment Due to Lack of a High-Energy Line Break Barriers (← links)
- IR 05000335/1998007 (← links)
- ML17229A791 (← links)
- ML14287A292 (← links)
- ML14129A350 (← links)
- ML13296A584 (← links)
- ML13291A294 (← links)
- ML13290A002 (← links)
- ML13280A089 (← links)
- ML13280A057 (← links)
- ML12335A435 (← links)
- ML12290A087 (← links)
- ML11356A157 (← links)
- ML11222A045 (← links)
- ML11213A132 (← links)
- ML11132A118 (← links)
- NRC Generic Letter 1988-03 (← links)
- NRC Generic Letter 1987-16 (← links)
- NRC Generic Letter 1987-11 (← links)
- NRC Generic Letter 1987-13 (← links)
- ML18024A398 (← links)
- ML17179A529 (← links)
- IR 05000261/2018010 (← links)
- ML17263A748 (← links)
- ML17263A568 (← links)
- ML17261A690 (← links)
- ML17261A676 (← links)
- ML17261A610 (← links)
- ML17251B094 (← links)
- ML17251B093 (← links)
- ML17251A253 (← links)
- NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 2 (← links)
- NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1 (← links)
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.6, Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping (← links)
- L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures (← links)
- RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems (← links)
- 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 3.6-1 - 3.7-223 (← links)
- NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 1, Introduction and Summary (← links)
- NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 (← links)
- NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 (← links)
- ML110320093 (← links)
- ML103010299 (← links)
- ML102460635 (← links)
- ML102170077 (← links)
- ML102120049 (← links)
- ML101940382 (← links)
- ML101940381 (← links)
- ML101940380 (← links)
- ML101940376 (← links)
- ML101940375 (← links)
- ML101940374 (← links)
- ML101940373 (← links)
- ML101940366 (← links)
- ML101940365 (← links)
- ML101810146 (← links)
- ML101760198 (← links)
- ML101400144 (← links)
- ML101270388 (← links)
- ML093100130 (← links)
- ML083330276 (← links)
- ML082540140 (← links)
- ML081490118 (← links)
- ML080850253 (← links)
- ML080390239 (← links)
- RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems (← links)
- NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix a (← links)
- ML043280007 (← links)
- LIC-13-0155, Supplemental Response to Request for Additional Information (RAI) for Fort Calhoun Station (FCS) Exigent License Amendment Request (LAR) to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containme (← links)
- LIC-13-0148, Response to Request for Additional Information (RAI) for Fort Calhoun Station (FCS) Exigent License Amendment Request (LAR) to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containment (← links)
- ML073410063 (← links)
- ML072320121 (← links)
- ML071630230 (← links)
- ML070530070 (← links)
- ML070290328 (← links)
- ML062290208 (← links)
- ML062200043 (← links)
- ML061930364 (← links)
- ML061780639 (← links)
- ML061380552 (← links)
- ML060230461 (← links)
- ML17212A047 (← links)
- NG-06-0384, Additional Information Regarding Inservice Testing Program Relief Request VR-01 (← links)
- ML18054B548 (← links)
- ML18155A450 (← links)
- ML18152B202 (← links)
- ML18017A426 (← links)
- RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2) (← links)
- L-2017-071, Submittal of Report of 10 CFR 50.59 Plant Changes, Tests and Experiments (← links)
- L-2016-088, Report of 10 CFR 50.59 Plant Changes - Docket No. 50-389 (← links)
- L-2014-125, Report of 10 CFR 50.59 Plant Changes (← links)
- L-2012-361, Report of 10 CFR 50.59 Plant Changes (← links)
- L-2012-059, Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request (← links)
- L-2011-361, Response to NRC Mechanical and Civil Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request (← links)
- NRC 2010-0069, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information (← links)
- ML18130A088 (← links)
- NG-17-0042, Fifth Inservice Inspection Interval Program Plan (← links)
- LIC-13-0149, Supplemental Response to Request for Additional Information (RAI) for Exigent License Amendment Request (LAR) to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containment (← links)
- LIC-13-0146, Exigent License Amendment Request 13-08 Revise Current Licensing Basis of Pipe Break Criteria for High Energy Piping Outside of Containment (← links)
- NG-11-0320, Fourth 10-Year Inservice Inspection Plan (← links)
- ULNRC-06043, Application for Amendment to Facility Operating License Npf -30 (LDCN 13-0016) Revision to FSAR Standard Plant Section 3.6 for Hdpe Crack Exclusion (← links)
- PNP 2016-015, Final Safety Analysis Report Update, Revision 32, Table of Contents (← links)
- L-PI-18-018, Updated Safety Analysis Report (USAR) Revision 35, Appendix I, Postulated Pipe Failure Analysis Outside of Containment (← links)
- L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009 (← links)
- ML19144A089 (← links)
- NG-06-0439, Fourth 10-Year Inservice Inspection Plan (← links)
- ML19207A017 (← links)
- ML18354A402 (← links)
- ML19242C728 (← links)
- RA-19-0253, Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building (← links)
- ML18247A227 (← links)
- ML19114A168 (← links)
- ML19302E051 (← links)
- ML19150A446 (← links)
- IR 05000305/2005010 (← links)
- ML051960178 (← links)
- ML051530399 (← links)
- ML19298B480 (← links)
- ML19331A520 (← links)
- ML19308A078 (← links)
- ML20011D478 (← links)
- ML20045H018 (← links)
- NRC 2004-0066, Annual 10 CFR 50.59 Summary Report for 2003 (← links)
- RC-03-0220, 10CFR50.54(a)(3) / 10CFR50.59 Biennial Report (← links)
- ML032541194 (← links)
- ML023470126 (← links)
- ML023250307 (← links)
- RC-02-0159, Criteria 2 Supplement to the Application for Renewed Operating License (← links)
- ML021920481 (← links)
- NG-02-0259, Submittal of Proposed Risk Informed Inservice Inspection Program for the Duane Arnold Energy Center (← links)
- ML020810033 (← links)
- ML20069D142 (← links)
- ML20083L797 (← links)
- ML20081K052 (← links)
- ML20106D925 (← links)
- ML20113H712 (← links)
- NRC-97-0043, Provides Info Re Recently Identified Issued Involving Effects of Postulated HELBs Inside Containment on EECWs & Utils Basis for Conclusion (← links)
- ML20147B967 (← links)
- ML20141B304 (← links)
- ML20134H221 (← links)
- ML20216A541 (← links)
- RA-20-0267, Proposed License Amendment Request to Revise Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of Containment Building - Responses to Request for Additional Information (← links)
- IR 05000245/1998212 (← links)
- ML20153C860 (← links)
- ML20153B507 (← links)
- IR 05000331/1998008 (← links)
- ML20150B943 (← links)
- ML20149D628 (← links)
- ML20149D597 (← links)
- ML20196C571 (← links)
- ML20196C132 (← links)
- ML20195H911 (← links)
- ML20198R954 (← links)
- ML20197B917 (← links)
- IR 05000369/1997017 (← links)
- ML20207H949 (← links)
- ML20207D675 (← links)
- ML20237G318 (← links)
- ML20237B055 (← links)
- ML20249C403 (← links)
- ML20339A057 (← links)
- ML20246E615 (← links)
- IR 05000298/1987030 (← links)
- IR 05000445/1987026 (← links)
- IR 05000302/1995015 (← links)
- ML20236A574 (← links)
- ML20236A558 (← links)
- ML20235U763 (← links)
- ML20217P065 (← links)
- IR 05000261/2021010 (← links)
- ML20211P928 (← links)
- ML20211J256 (← links)
- 3F0389-19, Forwards Pipe Rupture Analysis Criteria Outside Reactor Bldg Crystal River Unit 3, for Review.Util Chose to Update Existing Pipe Rupture Criteria to Include Technical & Regulatory Advances on line-by-line Basis (← links)
- 3F0598-01, Application for Amend to License DPR-72,proposing Changes to FSAR to Include Description of Use of GL 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements & NUREG/CR-2913,as Part of Licensing & Design Basis (← links)
- 3F0997-01, Submits Suppl to NRC Ltr Re Protection Against Dynamic Effects of Loca.In Addition,Issue Being Tracked by NRC as Inspector Followup Item 50-302/95-15-02.W/one Oversize Drawing (← links)
- 3F0997-14, Application for Amend to License,Consisting of License Amend Request 218,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR (← links)
- ML21210A135 (← links)
- ML21210A128 (← links)
- ML21201A147 (← links)
- ML20209A355 (← links)
- SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With (← links)
- 3F0298-17, Forwards List of Commitments,Conclusions Presented in 980130 Telcon,Description of long-term CAs Required to Resolve Conflicts within FSAR & Summary of Previously Docketed Correspondence Re Protection Against Effects of LOCA (← links)
- 3F0298-09, Provides NRC W/Actions Carried Forward as non-restart follow-up Items for Which Util Committed Future NRC Submittal or Where NRC Action on Submittal Pending (← links)
- 3F0198-34, Forwards Summary of Evaluation of Dynamic Effects of Pressurizer Surge Line LOCA Other Systems & Components,In Response to NRC 971222 Rai.Commitments Made by Util,Encl (← links)
- 3F0198-15, Provides Response to RAI Dtd 971209,re LAR 218 Concerning Rev of Makeup Sys Letdown Line Failure Accident Analysis (← links)
- 3F1188-17, Provides Update on Status of High Energy Line Break (HELB) Resolution Program.Util Unable to Locate Sufficient Documentation to Rely on as Permanent Resolution & Therefore Reestablishing Compliance W/Helb Design Basis (← links)
- 3F0988-16, Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks (← links)
- B12811, Forwards Util Responses to Staff Concerns Re NUREG-0824, Section 4.12, Design Codes,Design Criteria & Loading Combinations & Unresolved Items from SEP Topic III-7.B (← links)
- ML22005A084 (← links)
- ML21294A177 (← links)
- ML21179A027 (← links)
- ML21125A472 (← links)
- ML21125A293 (← links)
- ML21125A288 (← links)
- ML21104A354 (← links)
- ML21102A356 (← links)
- ML21286A238 (← links)
- ML22131A351 (← links)
- ML20147A039 (← links)
- ML22193A067 (← links)
- RC-94-0232, Forwards Eleventh Annual 10CFR50.59 Rept for VC Summer Nuclear Station.Rept Contains Brief Description of Changes & Mods Made to Facility or QA Program,As Described in FSAR & Fire Protection Evaluation Rept (← links)
- ML22340A136 (← links)
- ML23062A429 (← links)
- ML20059C668 (← links)
- IR 05000346/1993017 (← links)
- ML23151A461 (← links)
- TXX-6575, Advises That Due to Issuance of 870619 Generic Ltr 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, Further Work in Area Suspended.Generic Ltr Will Eliminate Need to Respond to NRC Request for Addl Info (← links)
- ML23173A037 (← links)
- TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station (← links)
- ML23181A135 (← links)
- ML23291A406 (← links)
- ML23193A870 (← links)
- ML24128A106 (← links)
- ML24128A099 (← links)
- ML24116A067 (← links)
- ML24109A106 (← links)
- ML24080A345 (← links)
- ML24159A169 (← links)
- ML23180A020 (← links)
- ML20210G161 (← links)
- NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads, (← links)
- 05000285/LER-1988-005, :on 880309,discovered Condition in Which Specific LOCA Could Incapacitate Instrumentation Feeding Protective Function,Resulting in Loss of Pressurizer Pressure Transmitters Following Spray Break (← links)
- 05000346/LER-1992-004, :on 920427,HELB Analysis Error Discovered. Caused by Use of non-conservative Assumptions by Impell Corp in Calculation of post-HELB Environ Qualification.Rept Also Submitted,Per 10CFR21.Calculations Reviewed (← links)
- 05000254/LER-1996-015-01, :on 960816,HPCI Sys Jet Impingement Support Baseplate/Concrete Expansion Anchors Were Improperly Installed,Due to Ineffective Work Practices & QA Program. Review Will Be Completed (← links)
- ML20086S961 (← links)
- RC-93-0068, Forwards Description of Methodologies Being Used for Reanalysis of Major Piping Connected to Delta 75 SG (Rem 6000-6),including Reactor Coolant Loop,Main Steam,Fw, EFW & SG Blowdown Piping (← links)
- ML19325C195 (← links)
- ML19268A123 (← links)
- ML19177A178 (← links)
- ML19154A283 (← links)
- ML19154A251 (← links)
- ML18304A035 (← links)
- LR-N980049, Forwards Rev 16 to Salem Generating Station UFSAR IAW Requirements of 10CFR50.71(e).Rev Contains Identified Text, Table & Figure Changes Required to Reflect Plant Configuration as of 970731 (← links)
- ML17335A539 (← links)
- ML17291A203 (← links)
- ML17251A250 (← links)
- IR 05000237/1988011 (← links)
- IR 05000220/1992003 (← links)
- ML102880003 (← links)
- ML102670740 (← links)
- ML101481059 (← links)
- 3F0208-05, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)
- 3F0805-09, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)
- ML25080A136 (← links)
- ML25080A241 (← links)
- ML25283A014 (← links)
- ML25307A015 (← links)
- ML25107A246 (← links)
- ML25105A272 (← links)
- Category:Generic Letter (← links)