Search by property

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

• ML18051B017  + (Forwards Rev 3 to Milestone Commitments on Suppl 1 to NUREG-0737 & Psar,Safety Parameter Display Sys, Per 830913 & 16 Submittals)
• ML20085L102  + (Forwards Rev 3 to Millstone Unit 2,Cycle 11 Core Operating Limits Rept)
• ML20094B169  + (Forwards Rev 3 to Moderate Energy Line Break Study. Rept Prepared in Accordance W/Requirements of GDC 4 of 10CFR50, App a & Branch Technical Position Asb 3-1 of NUREG-0800)
• ML20129K320  + (Forwards Rev 3 to Monticello Nuclear Generating Plant COLR for Cycle 18)
• ML20129K321  + (Forwards Rev 3 to Monticello Nuclear Generating Plant COLR for Cycle 18.)
• ML20217K317  + (Forwards Rev 3 to NFS-0145, Hope Creek Generating Station Colr,Cycle 7/Reload 6)
• ML20196F572  + (Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl)
• ML20147G571  + (Forwards Rev 3 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting,Responsibility Changes & General Descriptions of Responsibilities for Organizations)
• ML20147G575  + (Forwards Rev 3 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting,Responsibility Changes & General Descriptions of Responsibilities for Organizations)
• ML20151P559  + (Forwards Rev 3 to NOV-1000-87-003, Hope Creek SPDS Verification & Validation Program Plan. Document Revised to Reflect Redesigned Hope Creek SPDS as Presented in 870521 Staff Meeting)
• ML20205E374  + (Forwards Rev 3 to NRC Regulations Handbook (NUREG/BR-0053). Revs Reflect NRC Regulations Re Notice & Comment Provisions of Administrative Procedure Act & Recently Implemented Regulatory History Procedures)
• IR 05000311/1997007  + (Forwards Rev 3 to NRC Restart Action Plan for Plant,Units 1 & 2.Status of Restart Items Reflects Insp Up to & Including 50-311/97-07 & Includes Insp Rept 50-311/97-11)
• ML20077A684  + (Forwards Rev 3 to NSSS Equipment & Piping, Vol Viii to Seismic Margin Review)
• ML18038A325  + (Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed)
• ML18038A326  + (Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed)
• B13633, Forwards Rev 3 to Northeast Utils USNRC Read & Sign  + (Forwards Rev 3 to Northeast Utils USNRC Read & Sign)
• ML20076L583  + (Forwards Rev 3 to Nuclear Security Emergency Contingency Plan.Encl Withheld (Ref 10CFR73.21))
• ML20012G591  + (Forwards Rev 3 to ODCM, Inadvertently Omitted from Jul-Dec 1992 Semiannual Radioactive Effluent Release Rept)
• ML20096C099  + (Forwards Rev 3 to OSR/GP-1, WVDP Operational Safety Requirements)
• ML20199A020  + (Forwards Rev 3 to Ofc Ltr 19,incorporating Board Notification Guidance Enunciated in CLI-86-1,per Commission 860516 Approval of SECY-86-134.Ofc Board Notification Policy Must Be Revised Consistent W/Rev 3 to Ofc Ltr 19)
• ML20083F108  + (Forwards Rev 3 to Offsite Dose Calculation Manual. Rev Addresses NRC Questions & Completes Response)
• ML16152A286  + (Forwards Rev 3 to Offsite Dose Calculation Manual)
• ML20083D885  + (Forwards Rev 3 to Offsite Emergency Plan & Submits Outline of Changes Set Forth to Provide Aid in Understanding Effect of Changes)
• ML20236U274  + (Forwards Rev 3 to Operating Procedure X-FE-101-3, Onsite NDE Records Control & Revised Index Submitted W/ 1987 Inservice Exam of Selected Class I & II Components & Sys. Rev Corrects Typo on Page C-i)
• ML20214W509  + (Forwards Rev 3 to Operational QA Program, for Review & Acceptance)

• ML20091H761  + (Forwards Rev 3 to Operator Requalification Program)

• ML20095D295  + (Forwards Rev 3 to Overhead Handling Sys Review. Rept Revised,Per NUREG-0612,to Address Concerns Identified in Draft Technical Evaluation Rept on Control of Heavy Loads & Support Resolution of SER License Condition 7)
• ML20246N832  + (Forwards Rev 3 to Oyster Creek Nuclear Generating Station Mark I Containment Long-Term Program,Addendum to MPR-734 Plant-Unique Analysis Rept Torus.... Results Confirm Adequacy of Util Judgement Re Calculated Overstresses)
• PY-CEI-NRR-2038, Forwards Rev 3 to PDB-F0001, COLR for Perry Nuclear Power Plant Unit 1,Cycle 6 (Reload 5) & Rev 0 to J11-02581SRLR, Supplemental Reload Licensing Rept for Perry Nuclear Power Plant Unit 1,Reload 5,Cycle 6  + (Forwards Rev 3 to PDB-F0001, COLR for Perry Nuclear Power Plant Unit 1,Cycle 6 (Reload 5) & Rev 0 to J11-02581SRLR, Supplemental Reload Licensing Rept for Perry Nuclear Power Plant Unit 1,Reload 5,Cycle 6)
• ML20097D746  + (Forwards Rev 3 to PECO-COLR-L1R5, COLR for Limerick Generating Station Unit 1,Reload 5,Cycle 6)
• ML20203E164  + (Forwards Rev 3 to PECO-COLR-P2C12, COLR for Pbaps,Unit 2, Reload 11,Cycle 12. COLR Submitted to NRC in Accordance W/ Pbaps,Unit 2 Tech Specs Section 5.6.5.d)
• ML20198C667  + (Forwards Rev 3 to PECO-COLR-P3C12, COLR for PBAPS Unit 3, Reload 11,Cycle 12, Incorporating Revised ARTS flow- Dependent MCPR & MAPLHGR Thermal Limit Curves)
• VPN-051-98, Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers  + (Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers)
• ML18010A796  + (Forwards Rev 3 to PLP-106, Shearon Harris Unit 1,Cycle 4 Colr. Change Incorporates Section 2.7 to Specify Min Boron Concentration for Refueling Operations,Per Amend 30 to TS)
• ML18010A797  + (Forwards Rev 3 to PLP-106, Shearon Harris Unit 1,Cycle 4 Colr. Change Incorporates Section 2.7 to Specify Min Boron Concentration for Refueling Operations,Per Amend 30 to TS)
• ML20211B680  + (Forwards Rev 3 to PP-02, Accident Mitigation Sys Review & Rev 3 to PP-03, Process Review,Cmp Horizontal Slice, Which Incorporates Addl Reviews Performed by Technical Advisory Group)
• ML20134D473  + (Forwards Rev 3 to PSA Peer Review Certification Implementation Guideline, for Jan 1997)
• ML20082H665  + (Forwards Rev 3 to Page 6-2 of Reactor Security Plan.Page Withheld)
• ML17305A702  + (Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin 891224 Ltr)
• ML17305A701  + (Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin)
• ML20211G870  + (Forwards Rev 3 to Parsons Power Group Inc,Millstone Unit 2 Independent Corrective Action Verification Program Audit Plan (PLN-01))
• ML20081G368  + (Forwards Rev 3 to Penn State Breazeale Reactor (Psbr) Emergency Preparedness Plan, Including Editorial Changes, Update of Site Description,Changes to Assist in Better Classifying Situations & Changes Mandated by New 10CFR20)
• U-600031, Forwards Rev 3 to Physical Protection Plan for Storage of Unirradiated Nuclear Fuel at Plant.Rev Reflects Storage Intentions & Administrative Controls Implemented Since May 1983.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 3 to Physical Protection Plan for Storage of Unirradiated Nuclear Fuel at Plant.Rev Reflects Storage Intentions & Administrative Controls Implemented Since May 1983.Rev Withheld (Ref 10CFR73.21))
• BSEP-99-0127, Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl  + (Forwards Rev 3 to Physical Security & Safeguards Contingency Plan, for Brunswick Steam Electric Plant,Units 1 & 2.Without Encl)
• ML20095C425  + (Forwards Rev 3 to Physical Security Plan.Encl Withheld)
• ML20065L263  + (Forwards Rev 3 to Physical Security Plan.Plan Withheld)
• ML20012C073  + (Forwards Rev 3 to Physical Security Plan.W/O Encl)
• ML20096E912  + (Forwards Rev 3 to Physical Security Plan.Includes Rationale for Exclusion of Certian Class 1E Cable from Vital Areas. Rev Withheld (Ref 10CFR73.21))
• ML20084J936  + (Forwards Rev 3 to Physical Security Plan Re Miscellaneous Corrections &/Or Clarifications,Organizational Changes & Changes to Reflect as-built Conditions.Rev Withheld (Ref 10CFR73.21))
• FVY-86-113, Forwards Rev 3 to Physical Security Plan,Addressing Provisions of 860804 Amend to 10CFR73.55.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 3 to Physical Security Plan,Addressing Provisions of 860804 Amend to 10CFR73.55.Rev Withheld (Ref 10CFR73.21))
• ML20092L507  + (Forwards Rev 3 to Physical Security Plan for Protection of SNM of Low Strategic Significance.Advises That Major Changes in Rev Reflect Fact That SNM for AGN-201M Training Reactor Has Been Shipped Offsite.Rev Withheld (Ref 10CFR2.790(d)))