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Partial response to FOIA request for documents re three named individuals & involvement in licensing matters submitted by PEPCO prior to ASLB appointment.Forwards document listed in App A.
Accession Number: ML20040F238
Date Released: Saturday, November 7, 2020
Package Contents
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- ML20040F625 - Requests technical assistance in review of util 700226 application for authorization to construct & operate two identical BWRs on Schuykill River.Extract from review plan encl. (10 page(s), 4/22/1970)
- ML20040F628 - Submits schedule for receipt of questions in structural & instrumentation areas for reactors handled by BWR group. Questions should include input from seismic consultants. (1 page(s), 4/22/1970)
- ML20040F634 - Forwards amend to Technical Assistance Request BWR 1-4 re PSAR review.Addl areas include fuel mechanical design, thermal & hydraulic design & safety design basis. (3 page(s), 6/15/1970)
- ML20040F638 - Forwards request for addl info to complete application review.Questions concern matl presented in PSAR re seismic input design criteria for structures,sys & components. (4 page(s), 7/1/1970)
- ML20040F642 - Forwards request for addl info to complete application review.Questions relate to PSAR matl re containment & other Class 1 structures. (5 page(s), 7/2/1970)
- ML20040F644 - Forwards request for addl info to complete application review.Questions concern classification of BWR sys by quality groups for pressure containing components within reactor coolant pressure boundary. (4 page(s), 7/16/1970)
- ML20040F646 - Forwards requests for addl info for application review. Info required re reactor vessel matl surveillance program, reactor internal structures & seismic input criteria for structures,sys & components. (13 page(s), 7/20/1970)
- ML20040F647 - Advises that review of util application will follow same plan as that of Newbold Island,per encl memo.Questions also provided. (1 page(s), 8/4/1970)
- ML20040F653 - Provides info for Instrumentation & Electric Power Sys review of Newbold Island Nuclear Generating Station. Question re emergency power for Limerick encl. (10 page(s), 6/23/1970)
- ML20040F659 - Forwards formal question re determination of containment design adequacy as discussed w/applicant at 700819 meeting. (3 page(s), 9/10/1970)
- ML20040F663 - Forwards request for addl info to complete containment design review.Info required re initial conditions,feedwater & steam isolation valve closure time assumptions used to analyze recirculation line break. (4 page(s), 10/15/1970)
- ML20040F669 - Forwards request for addl info re seismic instrumentation to complete application review.Triaxial accelerograph must be installed in reactor containment to provided seismic response data. (5 page(s), 3/4/1971)
- ML20040F670 - Forwards evaluation of containment & Class I structural design based on PSAR.Foundation conditions acceptable. (7 page(s), 3/23/1971)
- ML20040F672 - Forwards request for addl info for PSAR review.Items reviewed include seismic input,seismic sys dynamic analyses, reactor internals & sys quality group classifications. (11 page(s), 3/27/1971)
- ML20040F674 - Summary of 710331 meeting w/ACRS Subcommittee on Limerick. No exemption requests should be issued for facility w/o full ACRS consideration. (2 page(s), 4/1/1971)
- ML20040F684 - Forwards request for addl info to complete application review.Info needed re dynamic effects induced in reactor coolant boundary piping,design of valves & reclassification of seismically designed sys. (5 page(s), 5/17/1971)
- ML20040F689 - Requests that Mechanical Engineering Branch 710517 request for addl info re facilities be translated into firm regulatory requirements to be made part of ACRS rept & safety evaluation. (1 page(s), 5/25/1971)
- ML20040F693 - Forwards safety evaluation re protection & emergency power sys for facilities.Outstanding areas include design criteria for cable installation & post-accident monitoring instrumentation. (8 page(s), 6/4/1971)
- ML20040F699 - Forwards hydrologic engineering summary for use in preparing ACRS rept on facilities. (5 page(s), 6/9/1971)
- ML20040F702 - Forwards final mechanical evaluation re facilities. (14 page(s), 6/29/1971)
- ML20040F706 - Requests that util be informed of ACRS 710810 ltr recommending increase in max ground acceleration.Initiative for further action should rest w/applicant. (1 page(s), 8/12/1971)
- ML20040F709 - Forwards evaluation of containment design basis re facilities,for use in safety evaluation preparation. (38 page(s), 8/23/1971)
- ML20040F715 - Responds to 710823 memo re design capabilities for containment vessel.Margin above calculated valves should be applied to cover uncertainties in defined LOCA,rather than redefining accidents. (1 page(s), 9/20/1971)