Pages that link to "B13352, Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl"
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The following pages link to B13352, Requests Exemption from Certain Requirements of 10CFR50,App J to Assure That Containment Leakage During Design Basis Event Will Not Exceed Applicable Leakage Limits. Justification Encl:
Displayed 50 items.
- B13340, Submits Results of Svc Water & Primary Auxiliary Bldg Equipment Operability Analyses Not Provided in 890428 Submittal of Results of ECCS Single Failure Analysis (← links)
- B13339, Forwards Addl Info Re Util 881026 & 890306 Revised Tech Specs Requests,Per NRC Request.Existing 8 H Shift Frequency Does Not Provide Enough Latitude within 8 H Shift Whereas 12 H Shift Would (← links)
- B13224, Forwards Request for Schedular Exemption from Requirements of 10CFR50,App J,Sections III.A.6.(b),III.D.2(a) & III.D.3. Exemptions Will Provide Relief from Requirements for Penalty Type a Test Intervals During 1989 Refueling Outage (← links)
- B13223, Provides Results of ECCS Single Failure Analysis of Electrical & Air Sys.Two single-failure Vulnerabilities Re Boundary Valve Between QA Category 1 & non-QA Piping & Failure of Svc Water Pumps During LOCA Discovered (← links)
- B13257, Informs That Util Will Not Be Able to Implement RCS Level Indication Mod Until End of Second Refueling Outage,Per Generic Ltr 88-17 (← links)
- B13283, Confirms That Independent Walkthroughs Conducted on Software of Seven Listed Foxboro Spec 200 Micro Configurable Block Types,Per Recent Telcons W/Nrc (← links)
- B13222, Forwards Fire Hazard Analysis & 10CFR50,App R,Compliance Review (← links)
- B13137, Requests Exemption from Certain Requirements of 10CFR50, App J,Sections III.C.1 & III.C.2 Re Type C Testing Requirements.Diagrams for Each Penetration Included in Attachment I (← links)
- A07863, Forwards Addl Info Supporting NRC Review of Atws/Auxiliary Feedwater Sys in Compliance w/10CFR50.62(c) & Westinghouse Generic Package Described in WCAP-10858P-A,Rev 1,Section 2-3,per 890302 Request (← links)
- A08061, Responds to NRC Re Violations Noted in Insp Rept 50-213/89-05.Corrective Actions:Valve PW-V-600 Placed in Locked Close Position & Labeled as Containment Isolation Valve & Procedures Re Containment Integrity to Be Reviewed (← links)
- B13179, Responds to NRC Station Blackout Rule Re Capability of Plant to Maintain Core Cooling & Containment Integrity. Procedure Changes Identified in Part B of Attachment 1 Will Be Completed in 1 Yr After Notification Provided by NRR (← links)
- B13194, Forwards New Switchgear Bldg Const Bimonthly Progress Rept 15,per 860930 Commitment (← links)
- B12623, Forwards Rev 15 to Plant Physical Security Plan.Rev Withheld (Ref 10CFR73.21 & 2.790(a)) (← links)
- 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 (← links)
- 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)) (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- B12502, Advises That Since Re Nuclear Engineering & Operations (Neo) Procedures Upgrades,Further Improvements & Refinements of Neo Procedures Made (← links)
- 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 (← links)
- A05805, Forwards Response to NRC Request for Addl Info Re Plant Crdr Implementation Plan,Per Suppl 1 to NUREG-0737.CRDR Summary Rept Will Be Provided by 880225 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- A06649, Updates 870805 Response to NRC Informing of Steps Taken to Correct Deviation Noted in Insp Rept 50-213/87-10. Review of Emergency Operating Procedures Will Be Completed by 880311.Simulator Training Matls Revised (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- B12755, Forwards Two Oversize Nonproprietary Reactor Cavity Pool Seal Drawings (← links)
- A06850, Forwards Addl Info Re Miscellaneous Amends/Search Requirements for Amend to Physical Security Plan,Per NRC 871005 Request.Encl Withheld (Ref 10CFR2.790) (← links)
- A06867, Forwards Addl Info Re NUSCO-151, Haddam Neck Plant Reanalysis of Non-LOCA Design Basis Accidents, Per NRC 871015 Request.Responses to Questions from 870630 Meeting & Revised Pages for NUSCO-151 Also Encl (← links)
- A06748, Forwards Response to NRC Topic Evaluations Status of Integrated Safety Assessment Program Topics & Review of Draft NUREG-1185.Attachment a Provides Discussion on Scope, Evaluation & Prioritization of Each Topic (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- A06800, Responds to NRC Re Violations Noted in Insp Rept 50-213/87-21.Corrective Actions:General Employee Training for Util Personnel as Well as Safety,Security & Emergency Plan Training for Nonutil Personnel Will Be Upgraded (← links)
- B13139, Forwards Haddam Neck Plant Semiannual Radioactive Effluents Release Rept Jul-Dec 1988. Annual Radioactive Effluents Dose Rept to Be Submitted in Mar 1989 to Include Assessment of Radiation Doses Due to Stated Effluents During CY88 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- B13019, Forwards Update on Isap Topic Reviews Discussed in Util ,Description of New Topics Being Added to Isap, Updated Integrated Implementation Schedule & Summary Table of Isap ARM Scores & Installation man-rem for Each Project (← links)
- 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 (← links)
- 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 (← links)
- B12594, Forwards Response to NRC 870427 Question 10 Re Nulap 5 (← links)
- B12690, Forwards Bimonthly Progress Rept 6 Re New Switchgear Bldg Const,Per 860930 Commitment (← links)
- 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 (← links)
- 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 (← links)