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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
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[ 'o' UNili t> St All s 8' '
'n NUCLEAR REGULAIORY COMMISslON h ' ' . 'f
. WASHINGTON, D. C. 20055
/ AUG 2 S 198
'+Q t
MEMORANDUM FOR: R. Mattson, Director, Division of System Safety I
FROM: Victor Stello, Jr., Director, Division of Operating Reactors l
SUBJECT:
OPERATING REACTORS EXPERIENCE MEMORANDA NO. 23, UPDATE PIPE CRACKS IN LARGE DIAMETER BWR PIPING SYSTEMS ,
By memorandum dated March 31, 1978, we advised you of a potentially significant incident of safe end cracking and pipe cracking in a foreign operating reactor. We met with representatives from the foreign country on August 22, 1978 and reviewed the results of the pipe crack investigations. -
We also received copies of four classified reports (confidential) which address this problem. We have concluded, based upon this recent inforTaation, that the occurrence of large diameter piping cracks is noteworthy. Further details are as follows:
- 1. The affected Unit is a dual cycle BWR. The piping involved is nominal 25" 0.0. stainless steel similar to type 304.
- 2. Cracking has been observed in the heat affected zone in the piping and cracking has been found at various locations in the safe ends.
- 3. All cracks originated from the ID and were comparatively shallow (< 5 mm depth in pipe and <10 mm depth in safe j
ends). Some cracks were extensive in length (600.mm in safe ends and 480 mm in pipe).
- 4. The cracks were found by visual examination of the inside surfaces af ter removal of the safe ends with a small -
piece of attached piping.
We are continuing to review this information to assess its signifiance with respect to US operating plants. We will provide copies of the translated documents as soon as they.are available.
Victar Stello, Jr., Director Division of Operating Reactors c * ' attached sheet E Y 4Y9 4 .
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Auli U 1978 cc: H. R. Denton . .'
E. G. Case S. Hanauer R. S. Boyd F. Schroeder DSS AD's D0R AD's D0R BC's DDR SL's J..Sniezek !
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