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List of results

• ML20235A462  + (Forwards Rev 1 to Safe Shutdown Capability Reassessment & Proposed Mods 10CFR50,App R, Per 840727 Commitment to Revise Section 6 of Plant App R Safe Shutdown Rept Dtd Jul 1984)
• RBG-19-244, Forwards Rev 1 to Safeguards Contingency Plan & Explanation of Major Changes.Encls Withheld (Ref 10CFR2.790(d))  + (Forwards Rev 1 to Safeguards Contingency Plan & Explanation of Major Changes.Encls Withheld (Ref 10CFR2.790(d)))
• ML19353B007  + (Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld)
• ML20100K182  + (Forwards Rev 1 to Safety Analysis for Hope Creek Generating Station SPDS-Display Design & Implementation, Per SER Outstanding Issue 15)
• ML20058F126  + (Forwards Rev 1 to Safety Assessment:Isolation Function of MOVs for HPCI & RCIC Steam Supply Line & RWCU Water Supply Line, Draft Generic Flooding Guidelines & Transmittal to Utils Reminding to Rereview Line Break Condition Guidelines)
• NRC-89-0227, Forwards Rev 1 to Safety Evaluation 89-0098 Re Control Ctr HVAC Ductwork,Per J Stang Request at 891025 Meeting.Safety Evaluation Written for Plant Configuration of Control Ctr HVAC & Standby Gas Treatment Sys Ductwork  + (Forwards Rev 1 to Safety Evaluation 89-0098 Re Control Ctr HVAC Ductwork,Per J Stang Request at 891025 Meeting.Safety Evaluation Written for Plant Configuration of Control Ctr HVAC & Standby Gas Treatment Sys Ductwork)
• ML19354D479  + (Forwards Rev 1 to Safety Evaluation 89-0098 Re Control Ctr HVAC Ductwork,Per J Stang Request at 891025 Meeting.Safety Evaluation Written for Plant Configuration of Control Ctr HVAC & Standby Gas Treatment Sys Ductwork)
• ML20101Q755  + (Forwards Rev 1 to Safety Evaluation Re IE Bulletin 84-03, Refueling Cavity Water Seal, in Response to . Differences in Seal Design from Haddam Neck Make Failure Probability Lower & Gross Failure Highly Unlikely)
• ML20134D497  + (Forwards Rev 1 to Safety Evaluation Secl 90-469.Revised Safety Evaluation Clarifies Section of ASME Code Associated W/Main Steam Safety Valves in Reference to CAE-90-315/CCE-90-310)
• ML17346B055  + (Forwards Rev 1 to Safety Evaluation Supporting Amends 99 & 93 to Licenses DPR-31 & DPR-41,respectively,changing Tech Specs to Support Integrated Program for Vessel Flux Reduction)
• ML20210G073  + (Forwards Rev 1 to Safety Evaluation for Operation of Catawba Units 1 & 2 W/Positive Moderator Coefficient, Clarifying & Supplementing 860606 & 0715 Reload Submittals)
• ML20140A645  + (Forwards Rev 1 to Safety Evaluation for Mod to Reactor Bldg Penetration R-536.Mod Will Deviate from Design Criteria in That High Pressure Tubing Conveying ultra-high Pressure Water Will Not Comply W/Ansi B31.1.Fee Paid)
• HBL-86-006, Forwards Rev 1 to Safstor QA Program & Description of Rev  + (Forwards Rev 1 to Safstor QA Program & Description of Rev)
• ML20214C271  + (Forwards Rev 1 to Salt Lake City Raip,Section 6.1 Re Field Density Control.Encl Change Per DOE Proposed Mod to Salt Lake City Radiological Assessment Plan for Tailings & Radon Cover Placement Moisture.Written Concurrence Requested)
• ML20028F818  + (Forwards Rev 1 to Sar,Keg Design Containers,Type B Package. Locations of Responses to 821029 Questions Indicated)
• RBG-34-747, Forwards Rev 1 to Sasr 91-16, Bounding Evaluation for River Bend 1 Heatup Rate Event. Describing 901130 Reactor Vessel Heatup of 119 F in 1 H Period  + (Forwards Rev 1 to Sasr 91-16, Bounding Evaluation for River Bend 1 Heatup Rate Event. Describing 901130 Reactor Vessel Heatup of 119 F in 1 H Period)
• RC-95-0148, Forwards Rev 1 to Sce&G VC Summer Nuclear Station ASME Section XI Inservice Exam Manual for 2nd Insp Interval  + (Forwards Rev 1 to Sce&G VC Summer Nuclear Station ASME Section XI Inservice Exam Manual for 2nd Insp Interval)
• ML20204J552  + (Forwards Rev 1 to Schedule for Transportation of Natural U Dioxide Shipments Due to Icy Road Conditions.Schedule of Dates of Departure/Arrival Submitted)
• ML19332D923  + (Forwards Rev 1 to Seabrook Plan for Massachusetts Communities & Seabrook Plan for Massachusetts Communities 1989 Plan/Procedures Update Resolution Tracking (Matrix))
• ML20098A849  + (Forwards Rev 1 to Seabrook Station Fire Protection of Safe Shutdown Capability (10CFR50,App R))
• ML20064N791  + (Forwards Rev 1 to Secl 90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation, in Response to NRC RAI Re Util 940321 Request for Emergency TS Amends)
• ML20151Q145  + (Forwards Rev 1 to Section 19.0 of Security Plan, Incorporating DOE Requirements in Rept K/1PT180, Rept of Special Team on Conceptual Safeguards & Security Plan for Pending Operation of Cpdf. Encl Withheld (Ref 10CFR2.790))
• ML19332E609  + (Forwards Rev 1 to Security Manual.Rev Withheld (Ref 10CFR73.21))
• SNRC-1939, Forwards Rev 1 to Security Plan for Fuel Storage in Spent Fuel Pool.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 1 to Security Plan for Fuel Storage in Spent Fuel Pool.Rev Withheld (Ref 10CFR73.21))
• ML20076G321  + (Forwards Rev 1 to Security Plan.Encl NUREG-0907 Worksheet Supports Proposed Armed Forces Response Force Size.Plan Withheld (Ref 10CFR73.21))

• ML20248C810  + (Forwards Rev 1 to Security Plan.Rev Withheld)

• LIC-89-1150, Forwards Rev 1 to Security Plan.Rev Withheld (Ref 10CFR73.21)  + (Forwards Rev 1 to Security Plan.Rev Withheld (Ref 10CFR73.21))
• ML20070Q776  + (Forwards Rev 1 to Security Training & Qualification Plan & Rev 3 to Security Contingency Plan.Encls Withheld)
• ML20133J731  + (Forwards Rev 1 to Seismic & Dynamic Qualification Summary & Status of Safety-Related Equipment, Facility Sys Turnover Status,Nsss Valve Number Correlation & Pump Listing,Per 850807 Meeting Re Sqrt/Pvort Site Audit)
• ML20133J734  + (Forwards Rev 1 to Seismic & Dynamic Qualification Summary & Status of Safety-Related Equipment, Facility Sys Turnover Status,Nsss Valve Number Correlation & Pump Listing,Per 850807 Meeting Re Sqrt/Pvort Site Audit)
• ML20096H011  + (Forwards Rev 1 to Seismic Evaluation Rept & Rev 1 to Relay Evaluation Rept, for Resolution of USI A-46,per GL 87-02)
• ML20093L713  + (Forwards Rev 1 to Seismic Reanalysis of Main Steam & Feedwater Piping Supports Inside Containment, Per SEP Topic III-6, Seismic Design Considerations)
• ML19327C230  + (Forwards Rev 1 to Semiannual Effluent & Waste Disposal Rept for Jan-June 1989. Changes Reflect New Dose Info from Abnormal Release to Toussaint,W/Exception of New Text on Pages B-7 & B-14 of App B)
• ML19327C231  + (Forwards Rev 1 to Semiannual Effluent & Waste Disposal Rept for Jan-June 1989. Changes Reflect New Dose Info from Abnormal Release to Toussaint,W/Exception of New Text on Pages B-7 & B-14 of App B)
• ML20153F863  + (Forwards Rev 1 to Semiannual Effluent Release Rept 7. Rev Consists of Revised Pages to Correct Compilation Errors in Reporting Total Ci Released of Tritium & Xe-135 Through Gaseous Pathways,As Addressed in Insp Rept 50-352/88-04)
• ML20215M365  + (Forwards Rev 1 to Semiannual Effluent Releases Rept 22, Jul-Dec 1986, Correcting Administrative Errors)
• ML20234E738  + (Forwards Rev 1 to Semiannual Effluent Release Rept 5. Rept Covers Period Jul-Dec 1986.Pages 2 & 3 of Attachment B Revised to Correct Typos Indicated by Vertical Bars in Margin of Pages,Per Tech Spec 6.9.1.8.W/o Rept)
• ML20247R013  + (Forwards Rev 1 to Semiannual Effluent Release Rept 9 for Jul-Dec 1988)
• ML20247L894  + (Forwards Rev 1 to Semiannual Effluent Releases Rept, Jan-June 1989)
• ML20087D124  + (Forwards Rev 1 to Sequoyah Nuclear Plant Unit 1,Cycle 6 Core Operating Limits Rept)
• ML20058K626  + (Forwards Rev 1 to Sequoyah Nuclear Plant Unit 1,Cycle 6 Core Operating Limits Rept)
• ML20057B746  + (Forwards Rev 1 to Sequoyah Nuclear Plant Unit 1 Cycle 7 Core Operating Limits Rept, Reflecting Redesigned Core Due to Titled Fuel Assembly H64 During Core Onload)
• ML18019A791  + (Forwards Rev 1 to Shearon Harris Nuclear Power Plant Crdr Final Summary Rept & Addl Info Re Human Engineering Discrepancies Listed in Draft Lll Technical Evaluation Rept)
• ML18019A792  + (Forwards Rev 1 to Shearon Harris Nuclear Power Plant Crdr Final Summary Rept & Addl Info Re Human Engineering Discrepancies Listed in Draft Lll Technical Evaluation Rept)
• ML18016A740  + (Forwards Rev 1 to Shnpp Cycle 9 Colr.Rev 1 Revises Movable Incore Detection Sys Operability Requirements to Specify That at Least 44 Detector Thimbles Are Required at Beginning of Fuel Cycle)
• HNP-98-179, Forwards Rev 1 to Shnpp Cycle 9 Colr.Rev 1 Revises Movable Incore Detection Sys Operability Requirements to Specify That at Least 44 Detector Thimbles Are Required at Beginning of Fuel Cycle  + (Forwards Rev 1 to Shnpp Cycle 9 Colr.Rev 1 Revises Movable Incore Detection Sys Operability Requirements to Specify That at Least 44 Detector Thimbles Are Required at Beginning of Fuel Cycle)
• SNRC-1489, Forwards Rev 1 to Shoreham Nuclear Power Station Prompt Notification Sys Rept, to Conform w/FEMA-REP-10 Guidance. Rev Made to Change Radio Station Wplr to Wcbs as Lead Broadcast Sys in Emergency Plan.Related Correspondence  + (Forwards Rev 1 to Shoreham Nuclear Power Station Prompt Notification Sys Rept, to Conform w/FEMA-REP-10 Guidance. Rev Made to Change Radio Station Wplr to Wcbs as Lead Broadcast Sys in Emergency Plan.Related Correspondence)
• ML20236P959  + (Forwards Rev 1 to Site Orientation Training Videotape for Use in Orientation Training for NRC Inspectors Requiring Unescorted Access at Facility.Handouts Used for on-station Training of New Employees Also Encl.W/O Stated Encls)
• RC-94-0160, Forwards Rev 1 to Snubber Relief Request RR-06,incorporating Util Response to NRC Requesting Clarification of TS Requirements as Indicated in Listed Paragraphs  + (Forwards Rev 1 to Snubber Relief Request RR-06,incorporating Util Response to NRC Requesting Clarification of TS Requirements as Indicated in Listed Paragraphs)
• ML20155C870  + (Forwards Rev 1 to Solid Radwaste Process Control Program & Rev 1 to Offsite Dose Calculation Manual. Revs Involve Format Changes Only)
• ML20095G608  + (Forwards Rev 1 to Solid Radwaste Sys Process Control Program, in Response to Meteorological & Effluent Treatment Sys Branch Request for Addl Info,Per 840808 Telcon. Preoperational Testing of Sys Scheduled for End of Month)