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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
- 3F0289-19, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0786-18, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0586-04, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0688-04, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0788-13, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0388-06, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0485-05, Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Rev Withheld (Ref 10CFR73.21))
- 3F0787-12, Forwards Rev 4 to Modified Amended Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan or Implementation.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Modified Amended Security Plan.Changes Do Not Decrease Safeguards Effectiveness of Plan or Implementation.Rev Withheld (Ref 10CFR73.21))
- ML18038A451 + (Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified)
- ML17055E538 + (Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified)
- IR 05000311/1997012 + (Forwards Rev 4 to NRCs Restart Action Plan for Salem Units 1 & 2.Status of Restart Items Reflects Insps Up to & Including 50-311/97-12)
- ML20206U765 + (Forwards Rev 4 to NSPNAD-8102-A, Reload Safety Evaluation Methods for Application to Prairie Island Units, Including Original Acceptance Criterion for Condition IV Events Per 860530 SER)
- ML20065H913 + (Forwards Rev 4 to North Anna Power Station Unit 1 ISI Program General Second Insp Interval)
- ML20063B696 + (Forwards Rev 4 to Nuclear Emergency Plan, Consisting of Changes to Listed Sections)
- ML20137Y034 + (Forwards Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program.)
- ML20137Y030 + (Forwards Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program)
- ML20141F138 + (Forwards Rev 4 to Nuclear Security Training & Qualification Plan, Per 10CFR50.4)
- ML20141F142 + (Forwards Rev 4 to Nuclear Security Training & Qualification Plan, Per 10CFR50.4)
- ML20138P400 + (Forwards Rev 4 to ODA-204, Preparation of Emergency Response Guidelines, Rev 0 to EOS-0.0, Rediagnosis & Rev 1 to Generic Plant Comparison, in Response to Preliminary License Condition Re Second Operating Cycle)
- TXX-4641, Forwards Rev 4 to ODA-204, Preparation of Emergency Response Guidelines, Rev 0 to EOS-0.0, Rediagnosis & Rev 1 to Generic Plant Comparison, in Response to Preliminary License Condition Re Second Operating Cycle + (Forwards Rev 4 to ODA-204, Preparation of Emergency Response Guidelines, Rev 0 to EOS-0.0, Rediagnosis & Rev 1 to Generic Plant Comparison, in Response to Preliminary License Condition Re Second Operating Cycle)
- ML20237H838 + (Forwards Rev 4 to Offsite Dose Calculation Manual. Rev Contains No Technical Changes.Future Manual Revs Will Be Reported in Semiannual Radioactive Effluent Release Repts, Per Tech Spec 6.13)
- ML20095F062 + (Forwards Rev 4 to Offsite Dose Calculation Manual, Incorporating Catawba Calculation Info.Rev Submitted Prior to Submittal of Semiannual Radioactive Effluent Release Rept for Jul-Dec 1984)
- ML20128Q919 + (Forwards Rev 4 to Offsite Emergency Plan for Facility. Rationale Underlining Rev 4 & Associated Concepts Explained. Rev 4 Changes Add More Detail to Plan & Procedures in Response to Radiological Assessment Coordinator Review)
- ML20236C607 + (Forwards Rev 4 to Operational QA Program, for Review & Acceptance)
- B17485, Forwards Rev 4 to Operational Readiness Plan for Millstone Unit 2.Plan Covers Restart Readiness,Operational Assessment, Startup & Power Ascension + (Forwards Rev 4 to Operational Readiness Plan for Millstone Unit 2.Plan Covers Restart Readiness,Operational Assessment, Startup & Power Ascension)
- ML20091A927 + (Forwards Rev 4 to Operator Requalification Program)
- ML20097D171 + (Forwards Rev 4 to PECO-COLR-L1R5, Core Operating Limits Rept for Limerick Generating Station Unit 1 Reload 5,Cycle 6)
- VPN-066-96, Forwards Rev 4 to PGE-1060, Trojan Nuclear Plant Permanently Defueled Emergency Plan + (Forwards Rev 4 to PGE-1060, Trojan Nuclear Plant Permanently Defueled Emergency Plan)
- VPN-008-98, Forwards Rev 4 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Changes Add Provisions for Proposed Option to Remove Reactor Vessel & Internals as Single Entity.Organization Changes to Section 2 Reflect Purchasing + (Forwards Rev 4 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Changes Add Provisions for Proposed Option to Remove Reactor Vessel & Internals as Single Entity.Organization Changes to Section 2 Reflect Purchasing)
- VPN-036-99, Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage + (Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage)
- ML20196C599 + (Forwards Rev 4 to Part a of Offsite Dose Calculation Manual (Odcm),Adding ODCM Rev 4 to Bottom of Each Page.Changes to Odcm,Part B Will Be Submitted Upon NRC Approval of Changes to Part a)
- ML20056G624 + (Forwards Rev 4 to Physical Security Plan.Info Withheld,Per 10CFR2.790(d))
- ML20095B656 + (Forwards Rev 4 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21))
- ML20024A876 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld)
- ML20078R397 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- ML20076E744 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- ML20094H818 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- ML20105C459 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- L-92-334, Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21))
- ML20042E295 + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(d)))
- RBG-20-089, Forwards Rev 4 to Physical Security Plan & Explanation of Changes.Rev & Explanation of Changes Withheld (Ref 10CFR2.790) + (Forwards Rev 4 to Physical Security Plan & Explanation of Changes.Rev & Explanation of Changes Withheld (Ref 10CFR2.790))
- ML20154H492 + (Forwards Rev 4 to Physical Security Plan for Surry & North Anna Power Stations & Associated Isfsis.Encl Withheld,Per 10CFR73.21)
- FVY-86-114, Forwards Rev 4 to Physical Security Plan,Addressing Provisions of Amend to 10CFR73.55(e)(1) & Memo Providing Supplemental Info to Support Rev.Encls Withheld (Ref 10CFR73.21) + (Forwards Rev 4 to Physical Security Plan,Addressing Provisions of Amend to 10CFR73.55(e)(1) & Memo Providing Supplemental Info to Support Rev.Encls Withheld (Ref 10CFR73.21))
- B12367, Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790 & 73.21) + (Forwards Rev 4 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790 & 73.21))
- ML20202G735 + (Forwards Rev 4 to Physical Security/Contingency Plan,Per 10CFR50.54(p).Plan Withheld)
- ML20134J271 + (Forwards Rev 4 to Physical Security/Contingency Plan for SQN Dtd 960910.Encl Withheld)
- BECO-92-131, Forwards Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program. Program Addresses Anomalies Indentified in Pump & Valve Inservice Testing Program TER + (Forwards Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program. Program Addresses Anomalies Indentified in Pump & Valve Inservice Testing Program TER)
- ML20127N264 + (Forwards Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program. Program Addresses Anomalies Indentified in Pump & Valve Inservice Testing Program TER)
- ML20234B145 + (Forwards Rev 4 to Pipe Stress Review Issues List (Ril).All Technical Issues Associated W/Discipline Closed.Still Waiting for S&W Calculation 15454-NZ(B)-GENX-035,Rev 2 to Verify Completion of Commitments Associated W/Ril 11)
- ML20135G086 + (Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request)
- AECM-85-0296, Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request + (Forwards Rev 4 to Plant Operations Manual,Administrative Procedures 01-S-04-2, Licensed Operator Requalification Training,Safety-Related, to Support NRC Review of Generic Ltr 84-14,per 850910 Request)