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List of results

• ML18096A117  + (Forwards Rev 2 to NFU-0039, Salem Reactor Physics Methods. Util Plans to Utilize in-house Physics & Reload Safety Evaluation Methodologies for 10CFR50.59 Evaluation of Unit 2,Cycle 9)
• ML20210H554  + (Forwards Rev 2 to NPPD CNS Third Interval Inservice Testing Program. Encl Revised to Include Revised Relief Requests RV-08,RV-09 & RV-13)
• LD-93-143, Forwards Rev 2 to NPX80-IC-DP790-01, Human Factors Program Plan for Sys 80+ (Tm) Std Plant Design, Plant Designers Operational Support Info Plan... & Rev 2 to Design Alternatives for Sys 80+ Nuclear Power Plant  + (Forwards Rev 2 to NPX80-IC-DP790-01, Human Factors Program Plan for Sys 80+ (Tm) Std Plant Design, Plant Designers Operational Support Info Plan... & Rev 2 to Design Alternatives for Sys 80+ Nuclear Power Plant)
• ML18102A700  + (Forwards Rev 2 to NRC Restart Action Plan for Salem,Units 1 & 2.Encl Rev Was Approved by Salem Assessment Panel in Meeting 96-09)
• ML20211G296  + (Forwards Rev 2 to NRR Ofc Ltr 43, Release of Draft Info - Policy on Control of NRC & Other Documents, Per 870211 Discussion)
• ML20072M443  + (Forwards Rev 2 to NSPNAD-8609, Qualification of Reactor Physics Methods for Application to Monticello for Approval by 950801.Rev 2 Describes New Methods Based on CASMO-3/ SIMULATE-3)
• ML20151P077  + (Forwards Rev 2 to Nine Mile Point Unit 2 Security Plan for SNM of Low Strategic Significance.Rev Withheld (Ref 10CFR2.790))
• ML20133D384  + (Forwards Rev 2 to Nonproprietary & Proprietary ATC-8019-1-P-A, Atcor AVRS-80 Vol Reduction Process. Proprietary Version Withheld)
• ML20081F337  + (Forwards Rev 2 to North Anna Unit 1 Inservice Insp Program for Component & Component Supports,Second Insp Interval & Rev 1 to North Anna Unit 1 Inservice Insp Plan for Components & Component Supports Second Insp Interval)
• ML20236P285  + (Forwards Rev 2 to Npdd CNS Strategy for Achieving Engineering Excellence. Summary of Changes Contained in Rev 2 Included as Attachment B)
• ML20045G018  + (Forwards Rev 2 to Nuclear Containers,Inc Overall QA Manual QA-3 for Protective Shipping Packages)
• B14523, Forwards Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program  + (Forwards Rev 2 to Nuclear Engineering & Operations (Neo) Procedure Neo 2.35, Pep Verification & Validation Program)
• ML20246M902  + (Forwards Rev 2 to Nuclear Security Emergency Contingency Plan.Rev Withheld (Ref 10CFR73.21))
• ML20198S528  + (Forwards Rev 2 to Nuclear Station Engineering Instruction Nsei CS-4, UHS Monitoring, to Be Used to Implement Tech Spec Administration Program for Monitoring & Maint of UHS, Per R Wescott Request)
• ML20035A452  + (Forwards Rev 2 to Nuclear Training Procedure TRN-31, Fire Brigade Training, in Support of Util 911211 Request for Mod of Periodicity in Which Annual Practice Sessions Conducted for Fire Brigade Personnel at Facilities)
• ML20005E205  + (Forwards Rev 2 to OSR-IRTS-3, Maint of Spare High Level Waste Storage Capacity)
• ML19332D715  + (Forwards Rev 2 to Odcm.Quantity of Radioactive Matl Contained in Pond Shall Be Limited.Rev Incorporates Requirement for Resin Sampling & Radioactivity Analysis)
• ML19332D716  + (Forwards Rev 2 to Odcm.Quantity of Radioactive Matl Contained in Pond Shall Be Limited.Rev Incorporates Requirement for Resin Sampling & Radioactivity Analysis)
• ML20046D455  + (Forwards Rev 2 to Ofc Ltr 500, Procedures for Controlling Development of New & Revised Generic Requirements for Power Reactor Licensees)
• ML20198B855  + (Forwards Rev 2 to Offsite Dose Calculation Manual,Nuclear Generation Site Unit 1 & Rev 17 to Offsite Dose Calculation Manual,Nuclear Generation Site Units 2 & 3)
• ML20137N776  + (Forwards Rev 2 to Offsite Dose Calculation Manual. Rev Incorporates NRC Comments Re Rev 1.Std Presentation of Deposition Model Provided,X/Q Equation Included & X/Q & D/Q Data Referenced by NRC Incorporated)
• ML20137N782  + (Forwards Rev 2 to Offsite Dose Calculation Manual. Rev Incorporates NRC Comments Re Rev 1.Std Presentation of Deposition Model Provided,X/Q Equation Included & X/Q & D/Q Data Referenced by NRC Incorporated)
• ML13324A447  + (Forwards Rev 2 to Offsite Dose Calculation Manual, Per Util 840914 Commitment.Rev Corrects Calculation for Total Body Liquid Dose & Removes Refs to Equations from Units 2 & 3 Offsite Dose Calculation Manual)
• L-83-185, Forwards Rev 2 to Offsite Dose Calculation Manual  + (Forwards Rev 2 to Offsite Dose Calculation Manual)
• ML17213B195  + (Forwards Rev 2 to Offsite Dose Calculation Manual.)

• ML20042G073  + (Forwards Rev 2 to Operating Procedures for Facility)

• ML20127N906  + (Forwards Rev 2 to Operational QA Plan)
• ML20127N909  + (Forwards Rev 2 to Operational QA Plan.)
• ML20247E554  + (Forwards Rev 2 to Operational Safety Requirement Manual TR/IRTS-7, Operational Safety Requirements)
• ML20150B441  + (Forwards Rev 2 to Operator Requalification Program, for Review & Approval.Program Revised in Order to Conform W/ ANSI/ANS-15.4-1977 & NUREG-1021,Rev 4 & Satisfy 10CFR55, App a Criteria)
• ML20090L692  + (Forwards Rev 2 to Operator Requalification Program)
• ML20154L415  + (Forwards Rev 2 to Operator Requalification Program, Per 880422 Request)
• PY-CEI-NRR-1817, Forwards Rev 2 to PDB-F0001, COLR for Perry Nuclear Power Plant,Unit 1 Cycle 5 (Reload 4) & Rev 0 to GE Rept 23A7227, Suppl Reload Licensing Rept for Perry Nuclear Power Plant Unit 1 Reload 4 Cycle 5  + (Forwards Rev 2 to PDB-F0001, COLR for Perry Nuclear Power Plant,Unit 1 Cycle 5 (Reload 4) & Rev 0 to GE Rept 23A7227, Suppl Reload Licensing Rept for Perry Nuclear Power Plant Unit 1 Reload 4 Cycle 5)
• ML20199E313  + (Forwards Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2, Reload 4,Cycle 5, Per TS Section 6.9.1.12.Rev Changes Max Permissible Recirculation Pump Motor Generator Set Scoop Tube Stop Setpoints)
• ML20217G991  + (Forwards Rev 2 to PECO-COLR-P3C12, COLR for PBAPS Unit 3 Reload 11,Cycle 12, IAW TS 5.6.5.d)
• ML20058J180  + (Forwards Rev 2 to PECP-COLR-L1R4, Core Operating Limits Rept for Limerick Generating Station Unit 1 Reload 4,Cycle 5)
• ML20132G245  + (Forwards Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Changes Update Plan to Reflect Provisions of Final Decommissioning Rule & Organizational Changes)
• ML20132G250  + (Forwards Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Changes Update Plan to Reflect Provisions of Final Decommissioning Rule & Organizational Changes)
• VPN-077-96, Forwards Rev 2 to PGE-1063, Suppl to Applicants Environ Rept, Which Allows Option of Removing Reactor Vessel & Internals as Single Component  + (Forwards Rev 2 to PGE-1063, Suppl to Applicants Environ Rept, Which Allows Option of Removing Reactor Vessel & Internals as Single Component)
• ML20135B295  + (Forwards Rev 2 to PGE-1063, Suppl to Applicants Environ Rept, Which Allows Option of Removing Reactor Vessel & Internals as Single Component)
• ML20082E357  + (Forwards Rev 2 to PLG-0507, STADIC4 Model for Frequency of Nonrecovery of Electric Power at Seabrook Station for Plant at Power & Shutdown)
• 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)