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A list of all pages that have property "Title" with value "Suppl 2 to Safety Evaluation Supporting Fire Protection Program". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML17258A823  + (Suppl 2 to Fire Protection Safety Evaluation Re Evaluation of Four Items in Addition to Eleven Provided in Suppl 1.All Itmes Acceptable Except Items 3.23 (Suppl 1),3.2.3 & 3.2.8)
  • ML20008E464  + (Suppl 2 to Fire Protection Safety Evaluation for Previously Unresolved Open Items)
  • ML20093A508  + (Suppl 2 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station)
  • IR 05000440/1984029  + (Suppl 2 to Integrated Design Insp Rept 50-440/84-29 on 850509-10.Major Areas Reinspected:Mechanical Sys,Mechanical Components,Electrical Power & Instrumentation & Control Sys)
  • ML20154L940  + (Suppl 2 to LAR to License DPR-22,revising Statement on Normal Shift Length & Correcting Typos)
  • ML20097C008  + (Suppl 2 to Large Break LOCA-ECCS Analysis W/Increased Enthalpy Rise Factor:K(Z) Curve)
  • ML20082M319  + (Suppl 2 to License Change Request 94-08,supporting Mod P00068-3,which Upgrades Major Components of TIP Sys to Correct Typo.Revised TS Page 186 Encl)
  • ML20081M133  + (Suppl 2 to Monthly Operating Rept for Sept 1983)
  • ML17296B314  + (Suppl 2 to Palo Verde Environ Rept,Ol Stage.Oversized Drawings Encl.Aperture Cards Available in PDR)
  • ML17300A918  + (Suppl 2 to Palo Verde Generating Station Unit 2 Startup Rept)
  • ML20214L840  + (Suppl 2 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept)
  • ML20044D093  + (Suppl 2 to Part 21 Rept Re Borg-Warner,6 Inch, 150 Gate Valve Having Friction Factor Higher than Industry Std Value of 0.3.Data Obtained as Part of EPRI MOV Test Program,Per GL 89-10.Valve Testing to Begin in Jul 1993)
  • ML20211F509  + (Suppl 2 to Petition for Immediate Action to Relieve Undue Risk Posed by Nuclear Power Plants Designed by B&W.* Lists Names to Be Added to 870210 Petition & Corrects Address for Save Our State from Radwaste)
  • ML20134G968  + (Suppl 2 to Preliminary Equipment Survivability Rept)
  • ML20101H416  + (Suppl 2 to Pressurizer Surge Line Thermal Stratification for B&W 177-FA Nuclear Plants,Summary Rept Fatigue Stress Analysis of Surge Line Elbows)
  • ML20024D836  + (Suppl 2 to Proposed Amend 98 to License DPR-54,revising Tech Spec Table 3.7-1 Re Undervoltage Relay Settings)
  • ML20204A377  + (Suppl 2 to Proposed Change 114 to License DPR-36,revising Tech Spec 3.11.5 to Add Five Manual Isolation Valves to List of Manual Containment Isolation Valves That May Be Respositioned W/O Implementing Compensatory Measures)
  • ML19329E040  + (Suppl 2 to Rancho Seco Psar.Reflects Changes in Type of Tendon Used for Reactor Containment Bldg post-tensioning Sys & in Type of Cooling Tower Used for Power Conversion Cycle Heat Rejection)
  • ML20151W350  + (Suppl 2 to Rev 1 to UT-AUSTENITIC-A, Suppl for Automatic Ultrasonic Exam of Dissimilar Metal Welds)
  • ML20116K213  + (Suppl 2 to Rev 2 to DC Cook,Unit 2 Cycle 5 5% Steam Generator Tube Plugging Limiting Break LOCA-ECCS Analysis: K(Z) Curve)
  • ML20151W355  + (Suppl 2 to Rev 2 to UT-AUSTENITIC-M, Suppl for Manual Ultrasonic Exam of Dissimilar Metal Welds)
  • ML20010A988  + (Suppl 2 to Revision 1 of Licensing Rept on High Density Spent Fuel Racks)
  • ML19263D152  + (Suppl 2 to SER)
  • ML19329A646  + (Suppl 2 to SER for Facility)
  • ML20137Z497  + (Suppl 2 to Safety Evaluation Re Submittal 1 to Rev 3 of CEN-152, C-E Emergency Procedure Guidelines. Submittal Acceptable for Implementation & Will Provide Improved Emergency Procedure Development Guidance)
  • ML19347A785  + (Suppl 2 to Safety Evaluation Supporting Fire Protection Program)
  • ML20003C527  + (Suppl 2 to Safety Evaluation Supporting Fire Protection Sys)
  • ML19317G632  + (Suppl 2 to Safety Evaluation Supporting Tech Spec Change Proposed 750312 by Util,Permitting Operation of Facility at 2,772 Mwt)
  • ML20154B947  + (Suppl 2 to Safety Evaluation for Browns Ferry Nuclear Plant)
  • ML20065E027  + (Suppl 2 to Seabrook Station Initial Startup Rept for June- Aug 1990)
  • ML19249B291  + (Suppl 2 to Site Suitability Environ Rept of Application for CP & Early Site Review)
  • ML20203N257  + (Suppl 2 to Special Rept 1-SR-85-018:on 850925,condenser Evacuation Sys high-range Monitor RU-142 Inoperable for More than 72 H Due to Failure in low-range Monitor RU-141.New Isolated Grounding Sys Will Be Installed After 860601)
  • ML17303A705  + (Suppl 2 to Special Rept 2-SR-86-008:on 860326,condenser Evacuation Sys high-range Radiation Monitor Declared Inoperable & Exceeded Tech Spec Limit.Caused by Moisture in in Process/Sample Flow Media Causing Flow Filter Clogging)
  • ML17305A903  + (Suppl 2 to Special Rept 2-SR-89-007:on 890929,radioactive Gaseous Effluent Monitors Declared Inoperable for Greater than 72 H Due to Frequent Low Flow Alarms.Caused by Limit Switch Out of Adjustment.Limit Switch Readjusted)
  • ML17310A994  + (Suppl 2 to Special Rept 2-SR-92-004:on 921222,PASS Declared Inoperable for Greater than Seven Days Due to Failure of Containment Air Flow Indicator & Indication of Water Leakage at PASS RCS Sample Septum.Pass Declared Operable on 930105)
  • ML17310A995  + (Suppl 2 to Special Rept 3-SR-92-006:on 921217,PASS Declared Inoperable for Greater than Seven Days Following Failure to Meet Pressurized Sample Portion of Acceptance Criteria for Monthly Functional Sr.Pass Declared Operable on 921226)
  • 3F0386-13, Suppl 2 to Special Rept 85-03:on 850807,intermediate- & high-range Channels of Gaseous Release Monitors RM-A1 & RM-A2 Not Calibr.Mod to Achieve Overlap & Calibr of Intermediate Channels Completed  + (Suppl 2 to Special Rept 85-03:on 850807,intermediate- & high-range Channels of Gaseous Release Monitors RM-A1 & RM-A2 Not Calibr.Mod to Achieve Overlap & Calibr of Intermediate Channels Completed)
  • ML20092K596  + (Suppl 2 to Special Rept Spr 84-001:on 840110,fire Doors Opened to Chilled Water Pump Rooms.Supplemental Rept Re 40-yr Equipment Qualification & Hazard Determination Issues Will Be Submitted on 840730.Also Reported Per Part 21)
  • ML20198A001  + (Suppl 2 to Startup Rept for 860215-0515)
  • ML20212C886  + (Suppl 2 to Startup Test Rept)
  • ML19309C569  + (Suppl 2 to TMI-1 PSAR, Answers to AEC Questions)
  • NPL-99-0405, Suppl 2 to TS Change Request 211,transmitting Text That Will Be Relocated to Pbnp FSAR with Respect to Manager Supervisory Staff Requirements.Suppl Provided Based on Comments Fromqa Branch of NRC  + (Suppl 2 to TS Change Request 211,transmitting Text That Will Be Relocated to Pbnp FSAR with Respect to Manager Supervisory Staff Requirements.Suppl Provided Based on Comments Fromqa Branch of NRC)
  • ML18036B149  + (Suppl 2 to TS Change Request 301 to Licenses DPR-33,DPR-52 & DPR-68,clarifying Original Amend & Incorporating Revised Rule Change to 10CFR50.36a(a)(2) Which Decreases Reporting Frequency for Radiological Effluent Rept.Updated ODCM Encl)
  • ML18036B150  + (Suppl 2 to TS Change Request 301 to Licenses DPR-33,DPR-52 & DPR-68,clarifying Original Amend & Incorporating Revised Rule Change to 10CFR50.36a(a)(2) Which Decreases Reporting Frequency for Radiological Effluent Rept.Updated ODCM Encl)
  • 3F1086-11, Suppl 2 to Tech Spec Change Request 139,amending License DPR-72 to Reduce Frequency of Diesel Generator Cold Fast Start Tests to Semiannual.Amend Fee Submitted W/Original Request on 851028.W/Certificate of Svc  + (Suppl 2 to Tech Spec Change Request 139,amending License DPR-72 to Reduce Frequency of Diesel Generator Cold Fast Start Tests to Semiannual.Amend Fee Submitted W/Original Request on 851028.W/Certificate of Svc)
  • ML20083H529  + (Suppl 2 to Third-Party Review of TMI-1 Steam Generator Repair. Js Wetmore 830822 & 0909 Ltrs Encl)
  • ML19327C172  + (Suppl 2 to Topical Rept BAW-10167, Justification for Increasing Reactor Trip Sys On-Line Test Intervals)
  • ML20150E888  + (Suppl 2 to Topical Rept Ur 85-225-A, ASEA-ATOM Control Rods for Us Bwrs, Re CR-85 Control Rods)
  • ML17305B514  + (Suppl 2 to, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46)
  • ML19329E042  + (Suppl 2,Attachment A,To Rancho Seco PSAR, Answers to Div of Reactor Licensing Questions Re Vsl Tendon Sys)
  • ML19329E043  + (Suppl 2,Attachment B,To Rancho Seco PSAR, Supplemental Info Re Vsl Tendon Sys)
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