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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML20105A894 + (Forwards Rev 2 to PRA North Anna Power Station,Svc Water Preservation Project,Part One, Final Rept & PRA for North Anna Power Station,Svc Water Preservation Project,Part 1, Supplemental Rept,Per Environ Qualification of CR Chillers)
- ML13317B336 + (Forwards Rev 2 to PRA-1-91-016 Probabilistic Risk Assessment Evaluation of Proposed CCW Heat Exchanger Allowed Outage Time)
- RBG-20334, Forwards Rev 2 to PSAR Chapter 17 Re Const QA Program, Effective 840401.Changes Consistent W/Good QA Practice + (Forwards Rev 2 to PSAR Chapter 17 Re Const QA Program, Effective 840401.Changes Consistent W/Good QA Practice)
- ML17333A073 + (Forwards Rev 2 to PVNGS Unit 2 Colr. Rev Replaces Pages 1, 2,3 & 7 of Colr,Unit 2,Rev 1.Ltr Does Not Make Any Commitments to NRC)
- ML17313A671 + (Forwards Rev 2 to PVNGS Unit 2 Colr. Rev Replaces Pages 1, 2,3 & 7 of Colr,Unit 2,Rev 1.Ltr Does Not Make Any Commitments to NRC)
- ML13310B078 + (Forwards Rev 2 to PWR Safety & Relief Valve Test Program, PORV Block Valve Adequacy Rept for Southern California Edison,San Onofre,Unit 1)
- ML18065A536 + (Forwards Rev 2 to Palisades Plant Colr)
- ML18065A537 + (Forwards Rev 2 to Palisades Plant Colr.)
- 3F0693-10, Forwards Rev 2 to Performance Testing Procedure PT-340, Acceptance Criteria. Procedure Submitted in Response to NRC Request for Voltage Dip Data from Most Recent Integrated Engineered Safeguards Actuation Test + (Forwards Rev 2 to Performance Testing Procedure PT-340, Acceptance Criteria. Procedure Submitted in Response to NRC Request for Voltage Dip Data from Most Recent Integrated Engineered Safeguards Actuation Test)
- ML20138D180 + (Forwards Rev 2 to Perry Operations Manual Inservice Exam Program. Inservice Insp Program for Piping,Identified in GL 88-01 Will Be Performed as Specified in Ref Correspondence)
- PY-CEI-NRR-1591, Forwards Rev 2 to Perry Operations Manual Inservice Exam Program. Inservice Insp Program for Piping,Identified in GL 88-01 Will Be Performed as Specified in Ref Correspondence + (Forwards Rev 2 to Perry Operations Manual Inservice Exam Program. Inservice Insp Program for Piping,Identified in GL 88-01 Will Be Performed as Specified in Ref Correspondence)
- BSEP-98-0216, Forwards Rev 2 to Physical Security & Safeguards Contingency Plan for Units 1 & 2.Encl Rev Does Not Decrease Effectiveness of Plan or Level of Security Provided.Rev Withheld,Per 10CFR73.21 + (Forwards Rev 2 to Physical Security & Safeguards Contingency Plan for Units 1 & 2.Encl Rev Does Not Decrease Effectiveness of Plan or Level of Security Provided.Rev Withheld,Per 10CFR73.21)
- ML20082E257 + (Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- ML20195D138 + (Forwards Rev 2 to Physical Security Plan,Per Amend 10 to License SNM-1050.Rev Withheld)
- HBL-87-051, Forwards Rev 2 to Physical Security Plan & Changes.Changes Do Not Decrease Effectiveness of Plan & Submitted Per 10CFR50.54(p).Plan & Changes Withheld (Ref 10CFR73.21) + (Forwards Rev 2 to Physical Security Plan & Changes.Changes Do Not Decrease Effectiveness of Plan & Submitted Per 10CFR50.54(p).Plan & Changes Withheld (Ref 10CFR73.21))
- ML20084J695 + (Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 10CFR2.790))
- RBG-17-225, Forwards Rev 2 to Physical Security Plan & Explanation of Major Changes to Facilitate Review.Rev & Explanation Withheld (Ref 10CFR2.790) + (Forwards Rev 2 to Physical Security Plan & Explanation of Major Changes to Facilitate Review.Rev & Explanation Withheld (Ref 10CFR2.790))
- ML20235Z681 + (Forwards Rev 2 to Physical Security Plan.Rev Incorporates Physical Description of Controlled Access Areas.Encl Withheld)
- L-92-178, Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)) + (Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3)))
- ML20067B087 + (Forwards Rev 2 to Physical Security Plan,Adding Section 4.a.(6) on Page 3 to Allow Visitors Such as Tours Into Controlled Access Area & Correcting Section 5.e(7) on Page 8 to State That UPS Located in RCA Not Caa.Encl Withheld)
- ML20202H074 + (Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(d)))
- ML20210B998 + (Forwards Rev 2 to Physical Security Plan.Addl 60 Days for Implementation of Security Sys closed-circuit Television Assessment Feature Described in Attachment B Requested.Rev Withheld (Ref 10CFR73.21))
- B12165, Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 2.790) + (Forwards Rev 2 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 2.790))
- ML20211M817 + (Forwards Rev 2 to Physical Security Plan for Surry & North Anna Power Stations & Associated Isfsi,Which Became Effective on 970922,per 10CFR50.54(p) & 10CFR72.186(b). Plan Withheld.No Commitments Made by Ltr)
- ML20113D186 + (Forwards Rev 2 to Physical Security/Contingency Plan.Encl Withheld)
- ML20100N976 + (Forwards Rev 2 to Physical Security/Contingency Plan.Rev Withheld)
- 3F0492-10, Forwards Rev 2 to Pipe Rupture Analysis Criteria Outside Rb,Crystal River Unit 3. Greatest Potential for Postulated Terminal End Rupture Will Occur at 3-inch End of 6-inch by 3-inch Reducer + (Forwards Rev 2 to Pipe Rupture Analysis Criteria Outside Rb,Crystal River Unit 3. Greatest Potential for Postulated Terminal End Rupture Will Occur at 3-inch End of 6-inch by 3-inch Reducer)
- ML20138J460 + (Forwards Rev 2 to Pipe Stress Review Issues List,Per Questions & Comments on Comanche Peak Review Team Plan & Requests Made in 851009 & 28 Open Item Ltrs)
- ML20072A783 + (Forwards Rev 2 to Plan for Partial Release of Stop Work Action 10 Refueling Bellows Nde)
- ML20083A850 + (Forwards Rev 2 to Plant Administrative Procedure PAP-0806, Oil/Chemical Release Contingency Plan)
- BSEP-93-0027, Forwards Rev 2 to Plant Notice Procedure PN-30, Integrated Recovery Methodology, to Support Change in Commitment to Address 921218 Confirmatory Action Ltr Re short-term Actions for Performance Improvement Program + (Forwards Rev 2 to Plant Notice Procedure PN-30, Integrated Recovery Methodology, to Support Change in Commitment to Address 921218 Confirmatory Action Ltr Re short-term Actions for Performance Improvement Program)
- ML20151U035 + (Forwards Rev 2 to Plant Physical Security,Guard Force Training & Safeguards Contingency Plans.Encls Withheld (Ref 10CFR2.790(d)))
- ML20096D454 + (Forwards Rev 2 to Plant Recovery Core Damage Assessment Methodology. Rept & Related Info Supplied in Re NUREG-0737,Item II.B.3, Post-Accident Sampling Capability, Form Basis for Resolution of SER License Condition B.17)
- ML20084K705 + (Forwards Rev 2 to Position Paper on Reg Guide 1.97 & Brunswick Response to NUREG-0737,Suppl 1 - Reg Guide 1.97 - Application to Emergency Response Facilities)
- ML20217H452 + (Forwards Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar). Rev Incorporating Revised,Detailed Schedule & Revised Cost Estimate,Will Be Submitted to Util)
- ML17305A409 + (Forwards Rev 2 to Post-Restart Actions, & Submits Changes in Scheduled Completion Dates &/Or Changes in Responsibilities for Completion of Items W/Listed Exceptions)
- ML17305A410 + (Forwards Rev 2 to Post-Restart Actions, & Submits Changes in Scheduled Completion Dates &/Or Changes in Responsibilities for Completion of Items W/Listed Exceptions)
- ML20058M833 + (Forwards Rev 2 to Prairie Island Nuclear Generating Plant Sbo/Esu Project Design Rept)
- ML20129A041 + (Forwards Rev 2 to Preservation of Assets Preventative Program, for Review & Approval.Meeting Requested to Discuss Comments.Ceretificate of Svc Encl)
- ML20129A046 + (Forwards Rev 2 to Preservation of Assets Preventative Program, for Review & Approval.Meeting Requested to Discuss Comments.Ceretificate of Svc Encl)
- ML20236M256 + (Forwards Rev 2 to Preservice Insp (PSI) Program ISI-P-010. Differences Between Approved Unit 1 PSI Program & Rev 2 to Unit 2 PSI Program Summarized.W/O Rev)
- ML20235F804 + (Forwards Rev 2 to Preservice Insp Program Relief Request 1NR-11,correcting Equipment Number for HX 1CV01AB)
- ML20079P016 + (Forwards Rev 2 to Preservice Insp Program Plan Tables & Plan Apps a & B)
- ML20207G149 + (Forwards Rev 2 to Private Fuel Storage,Llc Physical Protection Plan & Rev 1 to Contingency Plan & Training & Qualification Plan.Plans Withheld from Public Disclosure Per 10CFR73.21)
- B13099, Forwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl + (Forwards Rev 2 to Probabilistic Safety Study Update.Advises That Study Update Will Be Integral Part of Util Response to Generic Ltr 88-20.W/three Oversize Figures Encl)
- ML20205E693 + (Forwards Rev 2 to Procedure 105.3, Maint of Oyster Creek Environ Qualified Equipment, for Forthcoming Audit,Per Request)
- ML17320A408 + (Forwards Rev 2 to Procedure 12 PMP 3150 PCP.001, Radwaste Process Manual, Per Requirement of Radiological Effluent Tech Spec (RETS) Section 6.14.NRC Approval Requested Prior to RETS Implementation Date of 830415)
- ML17320A409 + (Forwards Rev 2 to Procedure 12 PMP 3150 PCP.001, Radwaste Process Manual, Per Requirement of Radiological Effluent Tech Spec (RETS) Section 6.14.NRC Approval Requested Prior to RETS Implementation Date of 830415)
- ML20098D904 + (Forwards Rev 2 to Procedure AQ1.002, Station Operating Procedures & Emergency Response Procedures,Per 840907 Telcon Concerning B Kennedy Review of Emergency Operating Procedures Generation Package)
- RBG-20968, Forwards Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage, Completing Util Response to Criteria 2 of SER Confirmatory Item 50 Re NUREG-0737, Item II.B.3 + (Forwards Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage, Completing Util Response to Criteria 2 of SER Confirmatory Item 50 Re NUREG-0737, Item II.B.3)
- ML17251A630 + (Forwards Rev 2 to Procedure PT-32.5, Reactor Trip Breakers a & B Train Response Time Testing & Rev 7 to Procedure M-32.2, DB-50 Reactor Trip Circuit Breaker Insp..., in Compliance W/Generic Ltr 83-28,Items 4.2.1 & 4.2.2)