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Nitrogen +, Carbon +  and Lead +

10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50 Appendix G +, 10 CFR 5#O +  and 10 CFR 50.55a#g +

GO2-11-201, Amendment 61 to Final Safety Analysis Report, Appendix J, Shielding Evaluation Report +, GO2-80-172, Forwards SRV Loads - Improved Definition & Application Methodology for Mark II Containments, Prepared by Burns & Roe,Inc.Rept Withheld (Ref 10CFR2.790) +, GO2-81-146, Forwards Revised Cable Separation Criteria in Response to NRC 810504 Request.Circuits Will Be Modified as Necessary to Comply W/New Criteria.Deviations Not Included in Revision Will Be Addressed in Chapter 8 of FSAR +, GO2-81-322 +, GO2-81-524, Forwards Results of Suppression Pool Temp Transient analysis.In-plant Test Will Be Conducted to Measure Difference Between Local & Bulk Pool Temps During Main Steam Valve Discharge +, GO2-79-156 +, GO2-81-279 +, GO2-81-563, Forwards Licensing Review Group App I to Fsar.App Will Be Included in Amend 23 +, GO2-82-672, Forwards marked-up FSAR Pages Submitting Addl Info Re Internally Generated Missiles (Outside Containment),Per 820528 Commitment.Info Closes Outstanding SER Issue 2, NUREG-0892 +, GO2-81-532, Forwards Info on Apps G & H Per Agreement at 810401 Meeting.Responses to Questions 121.011 Through 121.019 Also Encl.Responses Will Be Included in Amend to FSAR +, GO2-80-279, Responds to Re Actions Taken to Preclude Cracking of Jet Pump Holddown Beams.Reducing Tension Preload to 25 Kips on Beams Provides Adequate long-term Solution +  and GO2-81-268, Forwards Response to NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping. Mods to Reduce Occurrence of Intergranular Stress Corrosion Cracking Have Been Made +

05000397  +, 00358  +, 00322  +, 00387  +, 00388  +  and 00341  +

GO2-11-201, Amendment 61 to Final Safety Analysis Report, Appendix J, Shielding Evaluation Report +, GO2-80-172, Forwards SRV Loads - Improved Definition & Application Methodology for Mark II Containments, Prepared by Burns & Roe,Inc.Rept Withheld (Ref 10CFR2.790) +, GO2-81-146, Forwards Revised Cable Separation Criteria in Response to NRC 810504 Request.Circuits Will Be Modified as Necessary to Comply W/New Criteria.Deviations Not Included in Revision Will Be Addressed in Chapter 8 of FSAR +, GO2-81-322 +, GO2-81-524, Forwards Results of Suppression Pool Temp Transient analysis.In-plant Test Will Be Conducted to Measure Difference Between Local & Bulk Pool Temps During Main Steam Valve Discharge +, GO2-79-156 +, GO2-81-279 +, GO2-81-563, Forwards Licensing Review Group App I to Fsar.App Will Be Included in Amend 23 +, GO2-82-672, Forwards marked-up FSAR Pages Submitting Addl Info Re Internally Generated Missiles (Outside Containment),Per 820528 Commitment.Info Closes Outstanding SER Issue 2, NUREG-0892 +, GO2-81-532, Forwards Info on Apps G & H Per Agreement at 810401 Meeting.Responses to Questions 121.011 Through 121.019 Also Encl.Responses Will Be Included in Amend to FSAR +, GO2-80-279, Responds to Re Actions Taken to Preclude Cracking of Jet Pump Holddown Beams.Reducing Tension Preload to 25 Kips on Beams Provides Adequate long-term Solution +  and GO2-81-268, Forwards Response to NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping. Mods to Reduce Occurrence of Intergranular Stress Corrosion Cracking Have Been Made +

ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +, ML12011A174 +  and ML12011A174 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

General Electric +  and Magnetrol +

NRC Bulletin 79-14 +  and NRC Bulletin 80-07 +

NUREG/CR-1330 +, NUREG-0420, Forwards Sser 9 (NUREG-0420).W/o Encl +, NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, NUREG-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0528, Forwards SER (NUREG-0528) & Federal Register Notice of Availability +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +, NUREG-0776, Safety Evaluation on Followup Allegation Re Chugging Loads at Facility,Per Sser 3 (NUREG-0776) +  and NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

Regulatory Guide 1.97 +, Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.45 +  and Regulatory Guide 1.108 +

NEDO-10905 +, NEDO-24708A +, NEDO-21778 +, NEDE-21821 +, NEDE-24011 +, NEDE-21354 +, NEDE-24010 +  and NEDE-21534 +

Pennsylvania +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

Safe Shutdown +, Fire Barrier +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Feedwater Heater +, Scram Discharge Volume +, Stress corrosion cracking +, Loss of Offsite Power +, Exemption Request +, Earthquake +, Fuel cladding +  and Water rod +