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The following 200 pages are in this category, out of 26,789 total.
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- B12076, Confirms Compliance w/10CFR50.49 (Environ Qualification) Prior to Startup from Current Refueling Outage at Reverification Stage,Per
- B12083, Forwards Test Results of Physical Properties of Concrete Masonry Blocks Used as Fire Barriers at Facility,Including Sample Description,Physical Data,Compressive Strength, Absorption & Fire Rating
- B12085, Forwards Nonproprietary Haddam Neck Plant Isap Public Safety Impact Model Project Analyses Summaries & Proprietary Haddam Neck Plant Isap Public Safety Impact Model. Proprietary Rept Withheld (Ref 10CFR2.790)
- B12086, Provides Implementation Status for 10CFR50,App R Mods.Mods Implemented Per 10CFR50.48 & App R,Except for Exemptions Consisting of Revised Schedule for Completing Switchgear Room & Fire Barriers Containing Unrated Penetrations
- B12087, Requests Exemption from App R Requirement for battery- Powered Lighting Units for Emergency Lighting in Areas Where Impractical.Security Lighting or Portable Lighting Will Be Used in Event of Fire & Loss of Offsite Power.Fee Paid
- B12089, Requests Temporary Waiver of Compliance from Tech Spec 3.3.D Limiting Condition for Operation for Tube 37-73 in Steam Generator 2.Justification Listed.Tube Will Be Plugged During Next Inservice Insp
- B12090, Application for Amend to License DPR-61,changing Tech Spec 4.10.1 Re Inservice Insp of Steam Generator Tubes to Allow Tube 37-73 in Steam Generator 2 to Remain Unplugged During Cycle 14 Operation
- B12100, Withdraws 830502 Application to Amend License DPR-13 Changing Tech Specs Re Reactor Vessel Surveillance Capsule Removal Frequency.Revised Application for License Amend Will Be Submitted by 860801
- B12103, Revised Application for Amend to License DPR-61,changing Tech Specs Re Inservice Insp of Steam Generator Tubes
- B12104, Application for Amend to License DPR-61,revising Tech Specs 3.22 & 4.15 to Add Control Room Halon Sys & to Substitute 18 Smoke Detectors Associated W/Control Room Halon Sys for 10 Existing Smoke Detectors.Fee Paid
- B12105, Forwards Isap 1.03, Containment Penetration Evaluations, to Facilitate NRC Review of Project Analysis.Public Safety Impact Scores Considered Preliminary
- B12107, Clarifies Two Points in SER on 841114 Exemption from 10CFR50,App R,Subsections III.G.2 & III.G.3,re Min Number of Operators Needed for Safe Shutdown in Event of Fire & Status of Exemption Application for Svc Bldg Mens Locker Room
- B12111, Application for Amend to License DPR-61,changing Tech Specs to Formalize Surveillance Requirement Re Quadrant Power Tilt Ratio.Fee Paid
- B12112, Forwards Fire Protection Evaluation Shutdown Sys Availability, Per 860605 Meeting W/Nrc at Region I. W/O Encl
- B12115, Forwards Isap Topic 2.03, Atmospheric Steam Dump, in Response to NRC 850731 Request for Review of Planned Plant Improvement Projects
- B12117, Forwards Review of Topic 1.12 of Isap, Control Room Habitability & Topic 1.55 Radiation Protection Plans (NUREG-0737,Item II.D.3.4 & Item III.D.3.1,respectively)
- B12121, Forwards Reviews for Isap Topic 1.05, Seismic Structural Mods, Topic 1.09, Design Codes,Design Criteria,Load Combinations & Topic 1.57, Flooding of Compartments by Backflow, Per 850517 Commitment
- B12122, Forwards Revised Schedule for Completion of Haddam Neck Isap.Final Rept for Facility Isap Expected to Be Completed by Nov 1986
- B12127, Forwards Response to SALP Rept for Mar 1985 - Feb 1986 W/ Particular Emphasis on Recommendations for Individual Evaluation Categories
- B12130, Forwards Listed Summaries to Isap Topics,Including Isap 1.04, Seismic Qualification of Safety-Related Piping, in Response to 850731 Request.Public Safety Impact Scores Preliminary Since Analysis of Isap Not Completed
- B12136, Forwards Revised Pages to Attachments 2 & 3 of Re 10CFR50,App J Exemption Request Concerning Testing of Containment Isolation Valve in Reverse Direction & Addition of Penetration Requiring Schedular Exemption
- B12138, Remits Fee for Review of 860507 Application for Temporary Waiver of Compliance from Tech Spec 3.3.D for Tube 37.73 in Steam Generator 2
- B12143, Forwards Summary of Listed Projects Evaluated for Public Safety Impact Re Isap,Including Topics 1.16, ATWS, 1.19, Crdr & 2.08, Loss of DC Power
- B12144, Forwards Summary of Public Safety Impact Model Project Analyses for Isap Topics 1.02,1.07 & 1.18
- B12152, Forwards Conceptual Design Info for New Switchgear Room. Detailed Design Will Proceed in Good Faith According to Major Milestone Schedule,Pending NRC Approval of Design as Acceptable Means of Providing Alternate Shutdown
- B12155, Informs That Diesel Generator Annunciator Tests Completed on 860509.All Testing of Task Force Recommendations for Assurance That Errors Potentially Misleading to Operators Do Not Exist Completed
- B12159, Application for Amend to License DPR-61,changing Tech Specs to Upgrade Inservice Insp Surveillance Requirements for Reactor Vessel Per Rev 1 to Reg Guide 1.14.Fee Paid
- B12160, Forwards Confirmation of Required follow-up Actions from 860616-20 App R Insp.All Mods Will Be Completed by 870101
- B12162, Forwards Planned Mod of Containment Penetrations During 1987 Refueling Outage,Per 10CFR50,App J & Addl Info Supporting Permanent Exemption for Penetration P-80 (Fire Water to Containment Spray)
- B12167, Application to Amend License DPR-61,changing Recipient of Monthly Operating Repts in Tech Spec Section 6.5.1(d) to Conform to Latest NRC Guidance.Fee Paid
- B12175, Forwards Request for Exemption from 10CFR50.62(c) Requirements Re Initiation of Turbine Trip Under ATWS Conditions.Installation of Addl Trip Relays in Auxiliary Feedwater Initiation Circuitry Unwarranted.Fee Paid
- B12178, Informs That Interim Acceptance Criteria for Steam Generator Tubes W/Flaws in Roll Region of Tube Will Provide Adequate Tube Integrity for Remainder of Fuel Cycle,Per Reg Guide 1.121.Results of Destructive Exam Encl
- B12189, Forwards Reviews for Isap Topics 1.01, Switchgear Room Cooling Mods, 1.14.5, Fire Protection Improvements to Area S-1 & 1.14.6, Installation of Fire Pumps to Separate Charging Pumps
- B12190, Forwards Reviews for Isap Topic 1.02, High/Low Pressure Valve Interlocks, Isap Topic 1.07, Vital Bus Feed Realignment Mods, Isap Topic 1.11, Primary Auxiliary Bldg Ventilation Sys Mods & Isap Topic 1.19, Control Room..
- B12191, Forwards Reviews for Isap Topic 1.22, Emergency Response Facilities Info & Isap Topic 1.30, Reactor Protection Sys Isolation, Per Hl Thompson 850731 Request
- B12192, Forwards Reviews for Listed Isap Topics,Including Topic 1.44, Diesel Generator Reliability, Per 850517 Commitment
- B12193, Forwards Reviews for Listed Isap Topics,Including Topics 1.08, Seimic Mods to RCS & 1.13, Inadequate Core Cooling Instrumentation, Per 850517 Commitment
- B12194, Forwards Reviews of Isap Topics 1.18,1.26 & 1.42, Reactor Coolant Pump Seal Cooling Mods, Relief Valve & Safety Valve Testing & RCS Vents Tech Specs, Respectively
- B12195, Forwards Reviews for Isap Topic 1.27, Compliance W/10CFR50.46 & Isap Topic 1.28, Reactor Coolant Pump Trip. Review Includes Discussion of Safety Objective & Evaluation of Plant Design for Issue Addressed
- B12196, Forwards Reviews for Listed Isap Topics,Per 850517 Commitment Re Isap Program,Including Isap Topic 1.51, Sys Interactions, Isap Topic 1.54, Safety Implications of Control Sys & Isap Topic 1.58, Steam Binding..
- B12197, Forwards Reviews of Isap Topic 2.01, Secondary Side Chemistry Monitoring, Isap Topic 2.04, Modernize Reactor Protection & Control Sys & Isap Topic 2.05, Process Computer Replacement
- B12198, Forwards Reviews of Isap Topic 2.06, Evaluation of RCS Loop Isolation Valves to Mitigate Steam Generator Tube Rupture & Isap Topic 2.07, Auxiliary Pressurizer Spray Nozzle
- B12199, Forwards Reviews of Isap Topics 2.09,2.11 & 2.12 Re Reactor Coolant Pump Vibration Monitoring Sys Upgrade, Main Steam Sys Evaluation & Turbine Generator Trip Logic, Respectively,Per 850731 Request
- B12202, Forwards Reviews of Isap Topics 1.14 App R Mods, 1.14.3, App R Related Control Circuit Mods & 1.20, Spds
- B12204, Forwards Reviews of Isap Topic 1.14.1, Curbs Ramps Water Control Structures,Seals & Shields & Isap Topic 1.49, Steam Generator Tube Integrity
- B12205, Forwards Reviews of Isap Topic 2.02, Demineralized Water Storage Tank Oxygen Reduction & Isap Topic 2.10, Administration Bldg Upgrade
- B12206, Forwards Core Xiv Startup Physics Test Rept,Jul 1986. Rept Details Startup Physics Testing Conducted During May & June.Results of Addl Testing Re Three Loop Operation Will Be Submitted on or Before 861001
- B12207, Submits Summary of Facility PORV Setpoint Issue & Addl Info Supporting Conclusion That Evaluation Unnecessary to Assure Public Safety or Conform to NRC Requirements
- B12212, Forwards Summary of Qualification Analysis for Pipe Breaks Outside Containment,In Response to 860707 Request.Commits to Modify Equipment Outside Containment to Eliminate Reliance on feed-&-bleed in Compliance w/10CFR50.49
- B12218, Application for Amend to License DPR-61,authorizing Extension of License to 070629,40 Yrs from Date of Issuance of Ol.Fee Paid
- B12219, Requests Extension of 860428 Single Failure Exemption to Respond to Small Break Locas.Plant Mods Cannot Be Completed Until End of Cycle 15 Outage.Probabilistic Safety Study for Permanent Small Break LOCA Response Measures Encl.Fee Paid
- B12221, Forwards Addl Info Re Action Items Resulting from App R Insp on 860616-20 for Listed Topics & Brief Summary & Status Update of All Other Open Audit Issues.Response to Violations & Deviation Will Be Provided by 860903
- B12226, Requests That Due Dates to Discuss Results of Steam Generator Tube End Study Be Revised to Wk of 861020 & Submittal of Corrective Actions for Undefined Signals to 861114,due to Diversion of Resources for Unplanned Outage
- B12242, Application for Amend to License DPR-61,clarifying Tech Spec Section 1.8.2.b Definition of Containment Integrity & Effecting Surveillance Requirements for Manual Containment Isolation Valves.Fee Paid
- B12244, Forwards Reviews for Isap Topics 1.29, Flooding Evaluation, 1.53, Containment Emergency Sump Performance & 1.62, Feed & Bleed Sys Mod
- B12245, Forwards Reviews for Listed Isap Topics,Including Topic 1.43, Tech Specs from Generic Ltr 83-37, Per 850517 Commitment
- B12246, Forwards Reviews of Isap 1.14.2, Install New 480-Volt Load Ctr & Rearrange Equipment in Fire Area S-8, 1.14.4, Install Remote Shutdown Instrumentation Panel & 1.61, Pressurized Thermal Shock, Per 850517 Commitment
- B12247, Forwards Review for Isap Topic 1.16, ATWS, in Accordance W/Jf Opeka Providing for Discussion of Safety Objectives & Plant Design to Identify Specific Items for Consideration in Integrated Assessment
- B12248, Forwards Reviews for Isap 1.04, Seismic Qualification of Safety-Related Piping, Isap 1.50, Fracture Toughness of Supports & Isap 1.56, Bolting Degradation, in Accordance W/Jf Opeka
- B12249, Forwards Reviews of Isap Topics 1.59, Addl Low Temp Overpressure Protection & 1.60, Rcs/Rhr Suction Line Valve Interlock, Per 850517 Commitment
- B12250, Forwards Reviews for Isap Topics 1.24, Tech Spec Surveillance for Hydraulic Snubbers, 1.25, Tech Spec Surveillance for Mechanical Snubbers & 1.46, Inservice Testing for Diesel Generator Auxiliaries
- B12251, Forwards Addl Info Re Thermal Hydraulic Analyses in Plant Probabilistic Safety Study,In Response to Requests Made During 860812-15 Meetings.Core Exposure Prevented for Single Tube Rupture,But Not for Rupture of Five Tubes
- B12258, Clarifies 860819 Response to Potential Violation Item 86-17-08 Re Inadequate Emergency Lighting,Radio Communications & Breakers for Stated Valves Action Items, Per App R Insp During Wk of 860616
- B12259, Forwards Endorsement 97 to Nelia Policy NF-151 & Endorsement 85 to Maelu Policy MF-39
- B12262, Clarifies Commitment Made in Util Re Startup Physics Rept.Review of Safety Analysis,Amend & Rev to Startup Rept Required to Resolve Issue.Amend Request Will Be Submitted During Fourth Quarter 1986
- B12270, Forwards Reviews of Listed Isap Topics Re Generic Ltr 83-28, Including Topic 1.32, Item 2.1,Equipment Classification & Vendor Interface... & Topic 1.41, Item 4.5.1,Reactor Trip Sys Functional Testing, Per Util 850517 Commitment
- B12279, Forwards Major Milestone Schedule for Const & Implementation Phases of Erecting New Switchgear Bldg,Per NRC Approval of Exemption from Schedular Requirements of 10CFR50.48
- B12288, Forwards Summary of Safety Impact Model Project Analysis for Isap Topic 1.21, Reg Guide 1.97 Instrumentation
- B12289, Updates Status of Evaluation,Within Context of Isap,Of Proposed Plant Mod to Reduce Oxygen in Demineralized Water Storage Tank. Failure of Breather Valves on Sys Could Cause Unavailability of Feedwater Sys & Raise Core Melt Frequency
- B12291, Forwards Review for Isap Topic 1.03, Containment Penetration Evaluations, Per JW Opeka .Considers Topic Adequately Addressed
- B12292, Forwards Reviews for Isap Topics 1.23, Post-Accident Hydrogen Monitors & 1.63, Hydrogen Control, Per 850517 Commitment
- B12293, Forwards Reviews for Isap Topics 1.06, Wind & Tornado Loadings/Tornado Missiles & 1.31, Pipe Break Outside Containment, Per 850517 Commitment
- B12294, Forwards Reviews of Isap 2.13, Fire Detection Sys Upgrade, Isap 2.15, Long-Term Small Break LOCA & ECCS & Isap 2.16, Variable Overpower Trip Mods, Per 850731 Request
- B12295, Forwards Review for Isap 2.17, Zircaloy Clad Conversion, Per 850731 Request
- B12296, Forwards Reviews of Isap Topics 2.08, Loss of DC Power Study, Isap 2.14, Radiation Monitoring Sys Updrade, Isap 2.18, Nuclear Instrumentation Replacement & Isap 2.19, Pcb Oil-Filled Transformer, Per 850731 Request
- B12307, Clarifies 860312 Request for Exemption from Type C Testing Requirements of 10CFR50,App J for Reactor Coolant Charging Penetration P-8.Util Intends to Evaluate Mods to P-8 Pending Results of Integrated Assessment
- B12311, Forwards Review for Isap Topic 1.10, Torque Switch Mods, Per SEP Topic III-10.A.Torque Switch & Thermal Overload Protection Issues Adequately Addressed.Further Evaluation Ongoing
- B12318, Discusses NRC Concerns Re Reliance on feed-&-bleed to Address Issues Associated W/Environ Qualification & High Energy Line Breaks.Viewgraphs from 860917 Meeting Encl
- B12324, Submits Addl Info Re Use of Northeast Utils Fuel Rod Analysis Program Fuel Performance Code.Program Will Be Used to Perform steady-state Fuel Performance Analysis,Including Small Break LOCA ECCS Performance Evaluations
- B12337, Requests Approval to Defer Completion of Switchgear Room Halon Sys Mods to 1987 Refueling Outage or First 8-wk Outage Commencing After 870101.Performing Mods During Operation Could Have Significant Impact on Sys & Components
- B12340, Forwards Bimonthly Progress Rept 1 Re Const of New Switchgear Bldg
- B12343, Forwards Rev 2 to Environ Qualification Electrical Equipment Master List.Changes Made Based on Equipment Replacement & Clarification of Equipment/Component Certification Data
- B12346, Forwards Info on Fire Protection Re Wall Between Control Room & Computer Room.Wall Works in Conjunction W/Computer Room Halon Sys to Prevent Fires Which May Occur in Computer Room from Spreading to Control Room
- B12349, Forwards Nonproprietary Vols 1 & 2 & Proprietary Vol 3 to Isap,Haddam Neck Plant,Final Rept. Proprietary Vol Withheld (Ref 10CFR2.790).Affidavit Encl
- B12351, Forwards Rev 12 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a))
- B12360, Requests Temporary Waiver of Compliance from Tech Spec 3.11, Item B, Containment Integrity, to Allow Neutron Shield Tank Fill Valve CC-V-884 to Be Open Under Listed Conditions. Amend Request Will Be Submitted by 861223.Fee Paid
- B12373, Application to Amend License DPR-61,revising Tech Spec Section 3.6, Core Cooling Sys, to Reposition & Block Flow Control Valve RH-FCV-796 in Throttled Position During Remainder of Cycle 14 Operation.Fee Paid
- B12376, Informs That Util Will Attempt to Isolate Fire Water Sys from Penetration P-80 by Installing Blank Flange,If Necessary,During Next Integrated Leak Rate Test,Per Request at 860814 Meeting Re Util 10CFR50,App J Exemption Requests
- B12377, Application for Amend to License DPR-61,revising Tech Specs to Allow Manual Containment Isolation Valves to Be Opened Only During Performance of Periodic Maint & Clarifying Definition of Containment Integrity.Fee Paid
- B12382, Forwards Addl Info Supporting 861217 Proposed Amend to License DPR-61,revising Tech Specs to Permit Repositioning & Blocking of Flow Control Valve to Ensure Adequate Cooling in Event of Postulated Pipe Break in Core Deluge Piping
- B12385, Forwards Comments on NRC Final Draft Review of Northeast Utils Svc Co Probabilistic Safety Study,Submitted on 860331, as Part of Plant Isap Effort
- B12388, Submits Addl Info Re Exemption Request Per 10CFR50,App R for Separation of Redundant Safe Shutdown Equipment in Svc Bldg Mens Locker Room (Fire Area S-9).Addl Cables Identified That Run Through Cable Chase.Diagram Encl
- B12389, Proposed Tech Spec,Modifying Tech Spec 3.20, RCS Flow,Temp & Pressure to Include Three Loop Operation Flow Requirement & Tech Spec Figure2.2-2,reflecting Results of Three Loop Flow Measurement
- B12392, Responds to Notice of Violation & Proposed Imposition of Civil Penalties Resulting from Insp Repts 50-213/86-17 & 50-213/86-22 on 860616-20 & 0722-25 Re Occupational Whole Body Radiation Exposure in Excess of Regulatory Limit
- B12402, Rev 7 to Emergency Plan Implementing Procedure EPIP 1.5-11, Personnel Injuries, Rev 2 to EPIP 1.5-47, Operation of Wide-Range Gas Monitor During Accident Condition & Rev 3 to EPIP 1.5-48, Control Room Data Coordinator
- B12405, Provides Update on Implementation Status of Corrective Actions Discussed in Util 860630 Response to 860523 SALP Rept for 12-month Period Ending on 860228.Rept Focuses on LER Process & Plant Operations Review Committee Efficiency
- B12411, Forwards Bimonthly Progress Rept 2 Re New Switchgear Bldg Const,Per 860930 Commitment
- B12412, Forwards Summary of Results & Insights Gained from Fire PRA & Planned Actions to Reduce the Probabilistic Risk Due to Fires
- B12415, Provides Status of 860703 & 0819 Commitments Which Resulted from 860616-20 Fire Protection Insp & Audit.Util Made Mods to Control Room HVAC Sys Such That Exhaust Fan Will Automatically Shut Down in Event of Fire
- B12423, Forwards Rev 13 to Physical Security Plan Re Physical Protection,Per 10CFR50.54(p).Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))
- B12424, Informs That Rev 17 to Emergency Plan Implemented,Reflecting Changes in Emergency Action Level Tables & Editorial Corrections.Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of 10CFR50,App E
- B12427, Application for Amend to License DPR-61,revising License Conditions to Permit Possession & Use of Certain Byproduct Matls Currently Allowed by License 06-11682-01.Request for Termination of License 06-11682-01 Will Be Submitted Later
- B12428, Forwards Vols 1 & 2 to Updated FSAR for Haddam Neck Plant to Fulfill 870331 Milestone,Per Oct 1985 Commitment.Balance of FSAR Chapters Will Be Submitted on or Before 870630
- B12433, Semiannual Radioactive Effluents Release Rept,Jul-Dec 1986
- B12447, Discusses Temporary Arrangement for Monitoring Certain Plant Parameters W/Temporary Instrumentation in Cable Vault Following Control Room Fire,Per 860703 Commitment. Installation & Testing Completed Per 870101 Schedule
- B12450, Application to Amend License DPR-61,revising Tech Spec 4.12 Re High Energy Piping Sys by Expanding Augmented Inservice Insp Program to Include Break Locations on Steam Supply Lines to Auxiliary Feedwater Pumps
- B12454, Forwards Addl Info Re Rev 13 to Physical Security Plan.Info Withheld (Ref 10CFR73.21(b) & 2.790(a))
- B12455, Informs That Annual Emergency Preparedness Exercise Will Be Conducted on 870527.Listed Info Re NRC Personnel Attending Exercise Requested by 870401.Exercise Objectives & Schedule Encl
- B12461, Responds to NRC 870302 Request for Addl Info Re 861124 Request to Extend OL for 40 Yrs from Date of Issuance. Environ Impacts of Nuclear Fuel & Radwaste Transportation to & from Plant in Accordance w/10CFR51.52,Table S-4
- B12463, Advises That Util Conducted Fuel Misloading Event Evaluation for Plant,In Response to NRC 860417 Request.Procedural Controls & Sys Equipment Configurations Will Prevent Assembly Loading Errors.No Errors Committed
- B12476, Suppls 860930 & 1224 Requests for Extension of Single Failure Exemption.Description of Good Faith Efforts,Eccs Mods Resulting from Small & Medium LOCA Concerns & Single Failure Analysis of Core Deluge Piping Sys Encl
- B12480, Const Design Info Submittal:New Switchgear Bldg Const. W/38 Oversize Encl
- B12481, Forwards Addl Info Requested Informally During Dec 1986 & Feb 1987 Telcons,Providing More Details on Methodology Used to Determine Assumed Fluence Values
- B12501, Proposes Rev to Bases Section 2.4, Max Safety Settings - Protective Instrumentation. Rev Increases PORV Setpoint Above High Pressure Trip Setpoint
- B12502, Advises That Since Re Nuclear Engineering & Operations (Neo) Procedures Upgrades,Further Improvements & Refinements of Neo Procedures Made
- B12508, Radiological Environ Monitoring Program Annual Radiological Environ Operating Rept,1986
- B12511, Forwards Temporary Change to Physical Security Plan, Reflecting Temporary Mod to Protected Area Boundary.Change Withheld (Ref 10CFR73.21 & 2.790)
- B12512, Forwards Relief Request 2.0,requesting Relief from Performing Inservice Surface Exam of Eight nozzle-to-safe End Butt Welds for Inservice Insp Program,Code Category B-F, Item B5.10.Relief Requested by 870615.Fee Paid
- B12524, Forwards Revs to Nusco 151 Rept Re Reanalysis of non-LOCA Dbas,In Support of Design of Cycle 15 Reload.Major Changes in Analyses Include,Uncontrolled Rod Withdrawal from Subcritical,Steam Line Break & Boron Dilution
- B12532, Application for Amend to License DPR-61,revising Tech Specs Re RCS low-temp Overpressurization Protection Sys Set Point. Change Will Revise heat-up Curve for 22 Efpys.Fee Paid
- B12534, Bimonthly Progress Rept 4, New Switchgear Bldg Const. W/
- B12537, Proposed Tech Specs Supporting Cycle 15 Operation & Reflecting Upgraded Methods for Analysis of non-LOCA Events
- B12542, Proposed Tech Specs,Incorporating long-term Acceptance Criteria for Steam Generator Tubes W/Defects in Rolled Region
- B12543, Proposed Tech Specs 3.19 & 4.13 Re Snubber Testing & Surveillance
- B12544, Proposed Tech Specs,Incorporating Guarantee That New motor-operated Valves Scheduled for Installation During 1987 Refueling Outage Remain in Respective Positions,Causing No Adverse Effects to ECCS
- B12556, Clarifies 861231 Application to Amend License DPR-61, Revising Tech Specs Re Significance of Value Represented as Three Loop Power Level,Per NRC Request
- B12558, Withdraws 860312 Request for Exemption from 10CFR50,App J, Section III.A.4.(a) to Allow Continued Integrated Leak Rate Testing (ILRT) at Reduced Pressure of 15 Psig.Ilrt Will Be Conducted at Test Pressure of 40 Psig
- B12559, Forwards Addl Info Re Piping Stress Analysis for ECCS Mods, Per NRC 870520 & 0604 Requests.Results of Analysis Indicate That Piping Stress Levels for Deadweight,Thermal & Seismic Loading Conditions within Allowable Limits & Acceptable
- B12560, Proposed Tech Specs,Adding New Section Re Main Feedwater Isolation Valves
- B12561, Forwards Rev 14 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 2.790)
- B12565, Provides Info Re Design of New Rod Cluster Control Assemblies.Assemblies Will Be Placed Into Core During end- of-cycle 14 Refueling Outage.Mechanical Changes Listed
- B12569, Forwards Addendum 1 to NUSCO-152, Physics Methodology for PWR Reload Design, Summarizing Comparison of at-power Measurements to Predictions for Cycle 14.Requests Review & Approval by 870720 to Support Cycle 15 Operations
- B12576, Requests Exemption from 10CFR50,App J,Paragraph III.A.3, Requiring All Containment Integrated Leak Rate Tests Be Performed in Accordance W/Ansi N45.4-1972.Use of Mass Point Method (ANSI 56.8-1981) Requested.Fee Paid
- B12577, Forwards Connecticut Yankee Third 10-Yr Interval Inservice Test Pump & Valve Program Submittal & ...Inservice Insp Plan Summary Submittal, for Third 10-yr Insp Interval Commencing on 880101.Fee Paid
- B12578, Responds to NRC 870519 Concerns Over Implementation of Commitments (Ref Insp Rept 50-213/87-08).Efforts Underway to Improve Link Between Commitment Tracking & Work Assignment Sys.Util Performance Expected to Improve
- B12590, Forwards Addl Info Re NUREG-0737,Item II.D.1 Concerning Testing of Pressurizer PORV & Safety Valves at Plant,Per NRC 861212 Request.Response to Question 5 Not Yet Available Since Supporting Info Must Be Obtained from Contractor
- B12592, Responds to & Comments on Findings of SALP Board W/Emphasis on Board Recommendations for Individual Evaluation Categories.Response to Each of Board Recommendations for Plant Encl.Util Goal to Return to Category 1 in All Areas
- B12594, Forwards Response to NRC 870427 Question 10 Re Nulap 5
- B12595, Responds to NRC Verbal Request for Addl Info Supporting 861124 Application Amend to DPR-61 Extending License to 40 Yrs from Date of Issuance of Ol.Info Re Nonradiological Impacts Associated W/Extension of OL Encl
- B12600, Submits Info Re ECCS Mods,Per NRC 870707,10 & 15 Telcons. Attachment 1 Provides Random Stress Summary by Data Point for 8-inch Piping Cross Tie Between RHR & Safety Injection Sys.W/One Oversize Drawing
- B12601, Proposed Tech Spec 5.4, Containment, Deleting General Statements Made About Containment Penetrations & Associated Basis
- B12604, Proposed Tech Spec Changes Supporting Cycle 15 Operation
- B12605, Proposed Tech Specs,Modifying Calibr Requirements for Power Range Nuclear Instrumentation When Plant Operated at steady- State Reduced Power & Channels Adjusted to Provide Enhanced Overpower Protection
- B12610, Responds to Questions Posed During 870701 & 21 Telcon Re Fluence Calculations & Util Intentions Re Evaluation of PTS Upon Conversion from Stainless Steel to Zircaloy Clad Fuel. NRC Should Approve Rt PTS Evaluation Per 10CFR50.61
- B12619, Bimonthly Progress Rept 5:New Switchgear Bldg Const
- B12621, Notifies of Intent to Use ASME Code Section XI Code Cases N-234, Time Between Ultrasonic Calibr Checks & N-278, Alternate Ultrasonic Calibr Block Configuration I-3131 & T-434.3, for Reactor Pressure Vessel Exams
- B12623, Forwards Rev 15 to Plant Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 2.790(a))
- B12632, Forwards Responses to Questions Raised During 870630 Meeting Re Nusco 151 Concerning Reanalysis of non-LOCA Transients & Accidents in Chapter 10 of Facility Description & Safety Analysis
- B12633, Responds to Request for Addl Info Re Question 10 Concerning NULAP5.Current Results w/NULAP5 Shown to Predict All Test Data Pertinent to Major Phenomenon Associated W/Small Break LOCA Response.Evaluation Will Be Submitted by Nov 1988
- B12634, Forwards Response to NRC 861212 Question 5 Re NUREG-0737, Item II.D.1 Concerning Testing of PORVs & Safety Valves at Facility,Per Util & 870803 Telcon.Flow Rate Equal to Theoretical Flow for Fluid Transient Analysis
- B12640, Confirms That Piping Stress Analysis Considered Eccentric Mass of New Valves & Operators Being Installed as Part of ECCS Mods,Per NRC 870811 Telcon Request
- B12647, Forwards Relief Request 3.0 Requesting Relief from Performing Sys Hydrostatic Test of Svc Water Sys at Pressure in Conformance W/Requirements of IWA-5265(b).Fee Paid
- B12649, Responds to NRC 870818 Request for Addl Info Re Util 870601 Application for Amend to License DPR-61,providing long-term Acceptance Criteria for Steam Generator Tubes W/Defects Located in Rolled Region.Flaw Identification Discussed
- B12655, Forwards Semiannual Radioactive Effluents Release Rept, Jan-June 1987. Rept Includes Summary of Quantities of Solid Radwaste & Liquid & Gaseous Effluents.Annual Radioactive Effluents Dose Rept Will Be Submitted in Mar 1988
- B12662, Forwards Response to Listed Question Re Nusco 151, Haddam Neck Plant Reanalysis of Non-LOCA DBA, Per 870727 Telcon. Addl Info,Inadvertently Missing from ,Also Encl
- B12669, Forwards Relief Requests 5.0 & 4.0 for Relief from ASME Code Section XI Requirements for Inservice Insp of Category B-J Welds & Specific Valve Internal Surface Visual Exams, Respectively.W/One Oversize Drawing.Fee Paid
- B12685, Provides Status of Four Concerns Along W/Remaining Info to Resolve SEP Topic III-5.B, High Energy Pipe Break Outside Containment. Items Considered Adequately Addressed.Written Confirmation Requested
- B12687, Forwards Relief Request 6.0 for Relief from ASME Code Section XI Requirements for Sys Hydrostatic Test.Request Due to Variations in Elevation Test Boundary That Do Not Allow for Testing within Pressure Range Required by Code.Fee Paid
- B12690, Forwards Bimonthly Progress Rept 6 Re New Switchgear Bldg Const,Per 860930 Commitment
- B12691, Forwards Revised Tech Spec Pages Correcting Typos on Page 3-11,to Change Gpm to 230,000 Gallons & Page 3.31L,to Change Table 3.2-1 to 3.17-1
- B12695, Retracts 870729 Application for Amend to License DPR-61, Revising Tech Specs Re Feedwater Isolation Valves.New Proposed Rev W/Corrections & Clarifications Pertaining to Surveillance Requirements Will Be Provided at Later Date
- B12709, Comments on NRC 870902 Approval of Util 860930 & 870401 Requests for One Cycle Extension to Exemption from Single Failure Criterion That Had Been Granted on 860428.NRC Should Incorporate Comments in Future SER on Open Items Re HPSI
- B12718, Forwards Request for Relief from ASME Code Section XI Requirements for Pressurizer Upper & Lower Head to Shell Welds.Heads Cannot Be Volumetrically Inspected for Proper Length Beyond Edge of Weld Given as Welded Conditions
- B12726, Forwards Addl Info Re 1987 RCS Piping Inservice Insps,Per NRC Request During Insp 50-213/87-24.Info on Weld Data Cards & Radiographic Insp Repts for Reactor Coolant Loop Weldments Provided
- B12727, Proposed Tech Spec 3.12 Adding Operability Requirements on Offsite & Onsite Power Sources W/Limiting Conditions for Operation & Time Requirements for Corrective Actions
- B12755, Forwards Two Oversize Nonproprietary Reactor Cavity Pool Seal Drawings
- B12760, Informs of Intentions to Maintain Flexibility of Selecting Appropriate NDE Insp Techniques for Future Insps,Per Util 870827 Response to NRC Request for Addl Info Re Use of Equivalent Technology in Steam Generator Tube Insps
- B12761, Forwards Proprietary Rev 16 to Physical Security Plan.Rev Does Not Decrease Physical Security Plan Effectiveness.Rev Withheld (Ref 10CFR73.21(b) & 2.790(a))
- B12762, Responds to NRC Re Violations Noted in Insp Rept 50-213/87-20.Technical Errors & mis-statements Re Util Approach to Hot Particle Control Noted.Recommended Corrections to Specific Sections of Rept Listed
- B12765, Forwards Rev 15 to Emergency Plan Implementing Procedure EPIP 1.5-1, Emergency Assessment. Temporary Procedure Change 87-248 to Rev 14 to EPIP 1.5-1 Canceled & Should Be Removed.Pages 17-19 of Rev 14 Should Not Be Destroyed
- B12766, Provides Info Re Util Plans to Convert from Stainless Steel to Zircaloy Fuel Cladding.Meeting W/Nrc to Discuss Conversion Plans within 1 Month of Ltr Date Requested
- B12768, Submits Results of Exams,Analyses & Safety Assessment Re Discovery of Cracks in Control Rod Guide Tube Support Pins During 1987 Refueling Outage.Results Support Safe Cycle 15 Operation Despite Indicated Cracking in 25 Pins
- B12779, Informs That Due to Delays in Plant Const That Necessitated Temporary Changes to Protected Area Boundary,Original Protected Area Boundary Design Will Not Be Met by 871231. Extension of Change Until 880415 Acceptable Per 10CFR50.54
- B12780, Application for Amend to License DPR-61,changing Tech Specs by Adding Five Containment Isolation Valves to Table 3.11-1 & Deleting Two Containment Isolation Valves from Same Table. Fee Paid
- B12788, Informs of Plans to Conduct Annual Emergency Preparedness Exercise on 880603 or 04.Persons to Contact Listed
- B12797, Discusses Issue of Formally Incorporating Schedule for Correction of Human Engineering Discrepancies Identified During Crdr Into Isap.Issuance of License Condition Prior to 880225 Requested
- B12804, Forwards Bimonthly Progress Rept 8 Re New Switchgear Bldg Const,Per 860930 Commitment & 10CFR50,App R
- B12808, Provides Addl Info Requested at Meeting & Informs Staff of Status of Repairs to Thermal Shield.Summary of Evaluations Conducted in Conjunction W/Thermal Shield Repairs Encl
- B12813, Proposed Tech Specs Re Halon 1301 Sys & Fire Detection Equipment
- B12816, Forwards Addl Info Re Main Steamline Break Analysis & Reanalysis of non-LOCA Design Basis Accidents,Per 871216 Request
- B12819, Responds to 880205 Request for Addl Info Re Reactor Protection Sys Upgrade.Meeting Arranged W/Nrc on 880210 at White Flint Ofcs.Util Maintains RPS Upgrade Meets 10CFR50.59 Requirements & Does Not Need Prior Approval
- B12823, Forwards Comments on NRC 871112 SER Re Cycle 15 Reload Licensing Amend.Incorporation of Comments Into Sser Requested
- B12826, Informs That Util Plans to Conduct Annual Emergency Preparedness Exercise on 880604.Exercise Will Include Full Participation by State of CT & All Local Communities within Plume Exposure Pathway Epz.Tentative Schedule Encl
- B12828, Proposed Tech Specs,Renumbering Manual High Pressure Safety Injection Throttle Valves for Consistency W/Plant Loop Numbering Scheme
- B12830, Semiannual Radioactive Effluents Release Rept for Jul-Dec 1987
- B12833, Requests That NRC Change Confirmatory Order for Plant to Extend Due Date from 880225 to 1101 to Allow for Submittal of CRGR Summary Rept,Including Schedule for Resolution of Human Engineering Discrepancies
- B12839, Informs of Discrepancies in Fire Watch Protection Program, Per 871228 Missed Fire Watch Patrol During Personnel Shift Change & One on-duty Contract Fire Watch Technician Not Receiving Proper Training.Retraining Will Be Conducted
- B12845, Annual Radioactive Effluents Dose Rept for 1987
- B12847, Informs of Mods Completed by Util to Resolve Open SEP Topic VIII-2 Re Onsite Emergency Power Sys Diesel Generators.Util Installed Trip Bypass Circuitry for Generator Reverse Power & Generator Loss of Field Trips During 1984 Outage
- B12854, Forwards Proposed Changes to Modified Amended Security Plan Re Replacing Security Computer.Changes Withheld (Ref 10CFR2.790 & 73.21)
- B12857, Informs NRC of Type & Limits of Property Insurance Coverage for Facility
- B12860, Application for Amend to License DPR-61,adding License Condition Requiring Util to Implement & Maintain Integrated Implementation Schedule Program Plan
- B12861, Forwards Bimonthly Progress Rept 9 Re Major Milestones for Const of New Switchgear Bldg,Per 860930 Commitment & 10CFR50,App R
- B12866, Provides Justification for Continued Operation W/Reduction in ECCS Flowrate.Requests That Until Reanalysis Complete,Nrc Review Justification for Continued Operation Allowing Up to 80% Power.Power Presently Limited to 40%
- B12867, Forwards Public Version of Haddam Neck Plant Emergency Response Exercise for June 1988
- B12868, Forwards Addl Info Re Fire Protection of Safe Shutdown Capability,Per 10CFR50,App R & NRC 870930 Request.Rev to Plant App R Compliance Review,Reflecting Responses Should Be Submitted to NRC by 881231
- B12882, Forwards Addl Info Re Small Break LOCA Model NULAPS5,per 880317 Telcon.Info from NUREG-0065,info Re Response of Clad Swell & Rupture Model in Analysis & Info Requested in 880317 Conference Call Encl
- B12885, Provides Info on Open Items Re HPSI Pump Miniflow Mods & Gate Valve Flow Throttling Ability to Enable NRC to Complete Review of ECCS
- B12887, Radiological Environ Monitoring Program Annual Operating Rept,1987
- B12902, Assessment of Reverse Direction Testing of Containment Isolation Valves