ML20044G470
| ML20044G470 | |
| Person / Time | |
|---|---|
| Issue date: | 06/02/1993 |
| From: | Russell W, Speis T Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Beckjord E, Murley T Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20044G471 | List: |
| References | |
| RTR-NUREG-1477 NUDOCS 9306030160 | |
| Download: ML20044G470 (3) | |
Text
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i jf"%cI UNITED STATES t
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,j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001
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June 2, 1993
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MEMORANDUM FOR:
Thomas J. Murley, Director Office of Nuclear Reactor Regulation Eric S. Beckjord, Director Office of Nuclear Regulatory Research FROM:
William T. Russell Assnciate Director for Technical Assessment Office of Nuclear Reactor Regulation Themis P. Speis Deputy Director for Research Office of Nuclear Regulatory Research-
SUBJECT:
DRAFT NUREG-1477, " VOLTAGE-BASED INTERIM PLUGGING CRITERIA FOR STEAM GENERATOR TUBES - TASK GROUP REPORT" -
AVAILABILITY FOR PUBLIC COMMENT Attached for your information is a draft copy of NUREG-1477, " Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report."
This draft report presents the conclusions of a special NRC Task Group that was established to review the technical basis for voltage-based plugging criteria' applied to outer diameter stress corrosion cracking (0DSCC) of steam generator tubes. The charter of the Task Group was to review the technical bases for-and outstanding issues related to-interim approval-of voltage-based plugging criteria that had been approved for application to ODSCC and to prepare conclusions and recommendations concerning implementation of these criteria. All NRC staff participants in the Task Group have concurred with -
the draft report.
This draft report-is being placed in-the PDR, and a notice of opportunity for public comment on the draft report is being published in the Federal Reaister.
In addition, a copy of the draft report is being transmitted to all holders of
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an operating license or construction permit for PWRs by generic letter for-their information and comment. No action is being requested in this generic letter. Furthermore, the generic letter makes it clear that the Task Group conclusions and recommendations in the draft report are preliminary and predecisional.
After consideration of public comments, the report will be revised as
.neccessary. This report, when issued in final form, will serve as the technical basis for the forthcoming NRC staff generic position concerning the t
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use of voltage-based IPCs to address outer diameter stress corrosion cracking (ODSCC) at the tube-to-tube support plate intersections. The final staff generic position will be subject to the appropriate procedures necessary' to issue such a position.
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%fstonndW William T. Russell Associate Director for Technical-Assessment Office of Nuclear Reactor Regulation j
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Themis P. Speis 1
Deputy Director for Research Office of Nuclear Regulatory Research
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E. Jordan
Attachment:
1.
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use of voltage-based IPCs to address outer diameter stress corrosion cracking j
(0DSCC) at the tube-to-tube support plate intersections.
The final-staff generic position will be subject to the appropriate procedures necessary to issue such a position.
W @nA@/:
William T. Russell Associate Director for Technical Assessment -
Office of Nuclear Reactor Regulation
{ fist @rm@'T Themis P. Speis-Deputy Director for Research Office of Nuclear Regulatory Research cc:
E. Jordan i
Attachment.
1.
Draft copy of NUREG-1477 DISTRIBUTION:
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EMCB CHRON/RF " EMurphy GJohnson Treed Slewis RLobel JRichardson PDR (with Attachment)
AThadani TSpeis WRussell
- (with Attachment)
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