ML20151H295
| ML20151H295 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Monticello, Nine Mile Point, 05000000 |
| Issue date: | 12/08/1982 |
| From: | Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20151H203 | List:
|
| References | |
| FOIA-86-26, REF-GTECI-A-42, REF-GTECI-PI, RTR-NUREG-0313, RTR-NUREG-313, TASK-A-42, TASK-OR IEB-82-03, IEB-82-3, NUDOCS 8212220147 | |
| Download: ML20151H295 (2) | |
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MEMORANDUM FOR: ' Regional Administrators 3wl a$
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William J. Dircks Executive Director for Operations f
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SUBJECT:
BWR PIPE CRACK PROBLEMS k
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Recently there has been an increasing number of problems involving degra-dation and cracking in thick-wall large-diameter stainless steel piping at BWR plants.
As a result of the degradation identified in the recirculation systens piping in the reactor coolant pressure boundary at Nine Mile Point Unit 1 the NRC issued IE Bulletin 82-03 entitled, " Stress Corrosion Cracking in Thick-Wall large-Diameter Stainless Steel Recirculation Piping at BWR.
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Inspection pursuant to this IE Bulletin has revealed instances-of pip.ing degradation at Monticello and Hatch Unit 1.
Indications of piping degradation have also been identified at Hatch " Unit 1 during inspections conducted pursuant to NUREG-0313, Revision 1 (Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping).
NRR has generic responsibilities in this area, has chaired the Pipe Crack Study Groups, and has the lead responsibility for resolution of Generic Task A-42 (Pipe Cracks in Boiling Water Reactors).
Pursuant to that task, NRR published NUREG-0531 (Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactors), several generic letters, and NUR EG-0313.
NUREG-0313, Revision 1, published in July 1980, sets forth the NRC staff's revised acceptable nethods to reduce the intergranular stress corrosion cracking susceptibility of BWR ASME Code Class 1, 2, and 3 pressure boundary piping and safe ends, and provides inservice inspection requirements.
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The NRC needs a central point for dealing with these technical issues.
It is essential that the NRC response to the pipe crack problems be techni~cally correct, regionally consistent, and integrated with ongoing studies and research.
Accordingly, for any pipe crack problem that you judge requires substantive NRC review, I would like you to transfer responsibility for NRC action to NRR.
Because we have actions underway in this area, the following guidelines apply:
1.
Licensee responses to IEB 82-03 will be reviewed by the appropriate Region and the results forwarded to IE.
IE will evaluate and consolidate IEB 82-03 responses and provide the results to NRR.
NRR will employ this infonnation in formulating plans for NRC action.
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Substantj.a_1_pl ant-speci fic _ problems identif,1.ed during inspections pursuant to NOREG-0313 will be forwarded to NRR.
3.
Substantial p1 ant-specific problems with large-diameter safety
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related BWR piping will be forwarded to NRK.
4 NRR will evaluate and take appropriate licensing action regarding plant-specific repairs and modifications made as a result of pipe degradation identified pursuant to NUREG-0313 or IE Bulletin 82-03 inspections.
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Transfer of responsibility to NRR shall be made by memorandum to the Director, j
Division of Licensing, NRR.
The memorandum should transmit as much infonnation about the problem as you initially have available.
You will, of course, retain cognizance over any potential enforcement actions that may be related to pipe degradation problems (e.g., failure to report,,
management control weaknesses, violation of tech specs, etc.):
s (Sigried) William 1. Direks, Wil'liam J. Dircks Executive Director for Operations 1
cc:
H. R. Dentr;n R. C. DeYoung i
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