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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211K5591986-12-0303 December 1986
Package of Four Undated Memos Forwarding Part 21 & Deficiency Repts from Utils.Followup of Generic Aspects of Problem Requested.W/O Repts.Supporting Documentation Encl
ML20136E3411982-12-0808 December 1982
Submits Review of Memo Re Procedures for Cancelling Cps. Applicant Should Write Procedure to Allow Timely NRC Final Insp & Disposition
ML20054K9581982-06-15015 June 1982
Notification of 820622 Meeting W/Bwr Owners Group in Bethesda,Md to Discuss Hydrodynamic Pressure Loads in Control Rod Drive Lines Resulting from Fast Scram,Test Data Base & Proposed Methodology
ML20054M2141981-11-0909 November 1981
Discusses 811105 Telcon W/P Kirby of FBI Concerning Allegation of Falsified QA Records Re Atlas Machine & Iron Works
ML20215A5201981-02-0202 February 1981
Forwards 10CFR50.55(e) & Part 21 Telephone Rept Re Tdi Diesel Generator Turbocharger Thrust Bearings Defect. Followup on Generic Aspects of Problem Requested
ML20147D2191978-12-12012 December 1978
Based on Evidence to Date,Fault 5 Is Not Capable W/In Meaning of 10CFR100.Due to Apparent Association of Fault 5 to Faults Previously Described,Staff Does Not Feel Site Visit Is Necessary
ML20147C5181978-12-11011 December 1978
on 781114 TVA Reported the Discovery of a Reverse Fault 106 Feet North of Reactor'S east-west Center Line.Tva Will Submit Rept Detailing Description of Reverse Fault & Faults Relationship to Regional Geology
ML20148K9561978-11-0202 November 1978
Forwards NRC Memos Re Problems W/Pipe Support Base Plate Design.Ofc of Nuc Reactor Reg States That Problems Apply to Subj Facil.W/Encl ANO:7811020332 & 7811020336.)
ML20147D2661978-10-0606 October 1978
Forwards 780829 Internal NRC Memo Re Pipe Cracks Reported in Large Diameter Piping Sys of a Foreign Boiling Water Reactor (Bwr),The Significance of Which Is Being Reviewed Relative to Domestic Bwr'S
ML20147D3011978-08-29029 August 1978
Updates Info in 780331 Memo Re Pipe Cracks in Large Diameter Piping Sys of Foreign Boiling Water Reactors(Bwr).Concludes That Occurrence Is Noteworthy & Significance for Domestic Bwr'S Is Being Assessed
ML20235D2351975-11-24024 November 1975
Discusses Proposed CP Stage Health & Safety Review Schedule for Util Application for CP Docketed on 751107.Proposed Schedule Includes 761004 as Date for Issuing SER W/Final Sser Scheduled for 770110
1986-12-03
[Table view]
Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211K5591986-12-0303 December 1986
Package of Four Undated Memos Forwarding Part 21 & Deficiency Repts from Utils.Followup of Generic Aspects of Problem Requested.W/O Repts.Supporting Documentation Encl
ML20136E3411982-12-0808 December 1982
Submits Review of Memo Re Procedures for Cancelling Cps. Applicant Should Write Procedure to Allow Timely NRC Final Insp & Disposition
ML20054K9581982-06-15015 June 1982
Notification of 820622 Meeting W/Bwr Owners Group in Bethesda,Md to Discuss Hydrodynamic Pressure Loads in Control Rod Drive Lines Resulting from Fast Scram,Test Data Base & Proposed Methodology
ML20054M2141981-11-0909 November 1981
Discusses 811105 Telcon W/P Kirby of FBI Concerning Allegation of Falsified QA Records Re Atlas Machine & Iron Works
ML20215A5201981-02-0202 February 1981
Forwards 10CFR50.55(e) & Part 21 Telephone Rept Re Tdi Diesel Generator Turbocharger Thrust Bearings Defect. Followup on Generic Aspects of Problem Requested
ML20147D2191978-12-12012 December 1978
Based on Evidence to Date,Fault 5 Is Not Capable W/In Meaning of 10CFR100.Due to Apparent Association of Fault 5 to Faults Previously Described,Staff Does Not Feel Site Visit Is Necessary
ML20147C5181978-12-11011 December 1978
on 781114 TVA Reported the Discovery of a Reverse Fault 106 Feet North of Reactor'S east-west Center Line.Tva Will Submit Rept Detailing Description of Reverse Fault & Faults Relationship to Regional Geology
ML20148K9561978-11-0202 November 1978
Forwards NRC Memos Re Problems W/Pipe Support Base Plate Design.Ofc of Nuc Reactor Reg States That Problems Apply to Subj Facil.W/Encl ANO:7811020332 & 7811020336.)
ML20147D2661978-10-0606 October 1978
Forwards 780829 Internal NRC Memo Re Pipe Cracks Reported in Large Diameter Piping Sys of a Foreign Boiling Water Reactor (Bwr),The Significance of Which Is Being Reviewed Relative to Domestic Bwr'S
ML20147D3011978-08-29029 August 1978
Updates Info in 780331 Memo Re Pipe Cracks in Large Diameter Piping Sys of Foreign Boiling Water Reactors(Bwr).Concludes That Occurrence Is Noteworthy & Significance for Domestic Bwr'S Is Being Assessed
ML20235D2351975-11-24024 November 1975
Discusses Proposed CP Stage Health & Safety Review Schedule for Util Application for CP Docketed on 751107.Proposed Schedule Includes 761004 as Date for Issuing SER W/Final Sser Scheduled for 770110
1986-12-03
[Table view] |
Text
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/ DEC 12 is70 MEMORANDUM FOR: Olan D. Parr, Chuf Light Water Reactor: Branch #3, DPM FROM: J. Carl Stepp, Chief Geosciences Branch, DSE
SUBJECT:
FAULTING IN FUEL BUILDING EXCAVATION FOR PHIPPS BEND, UNIT 2, TAC # 4954 PLANT NAME: Phipps Bend Nuclear Power Plant, Units 1 & 2 LICENSING STAGE: CP DOCKET NUMBERS: 50-554 MILESTONE NUMBER: N/A RESPONSIBLE BRANCH: Sid Miner, LWR-3 On November 14, 1978 the Tennessee Valley Authority (TVA) informed Sandra Wastler that while excavating the foundation for the Phipps Bend, Unit 2 fuel building a reverse fault was discovered. In accordance with guidelines described in my August 14, 1976 memo to Olan Parr, TVA submitted the enclosed report providing a detailed description of the reverse fault and discussion of the fault's relationship to regional geology. As a result of the staff's review of this report, Fault #5 is considered to be associated with de--
formational activity related to the regions early geologic history, some time before 225 million years before present. Based on the evidence to date, this fault is not capable within the meaning of Appendix A to 10 CFR Part 100. Due to the apparent association of Fault #5 to the faults previously described, the staff does not feel a site visit is necessary.
Q joJ/dd-prJ.CarlStopp, Geosciences Branch Chief Division of Site Safety and Environmental Analysis
Enclosure:
As stated cc: R. Boyd S. Miner R. DeYoung S. oldberg D. Muller R R. Denise Local POR R. Jackson r-- ~~_.~.____ _
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