Information Notice 1993-52, Draft NUREG-1477, Voltage-Based Interim Plugging Criteria for Stem Generator Tubes.: Difference between revisions

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| issue date = 07/14/1993
| issue date = 07/14/1993
| title = Draft NUREG-1477, Voltage-Based Interim Plugging Criteria for Stem Generator Tubes.
| title = Draft NUREG-1477, Voltage-Based Interim Plugging Criteria for Stem Generator Tubes.
| author name = Grimes B K
| author name = Grimes B
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 15: Line 15:
| page count = 12
| page count = 12
}}
}}
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 14, 1993 NRC INFORMATION


NOTICE 93-52: DRAFT NUREG-1477, "VOLTAGE-BASED
WASHINGTON, D.C. 20555 July 14, 1993 NRC INFORMATION NOTICE 93-52:   DRAFT NUREG-1477, "VOLTAGE-BASED INTERIM


INTERIM PLUGGING CRITERIA FOR STEAM GENERATOR
PLUGGING CRITERIA FOR STEAM GENERATOR TUBES"
 
TUBES"  


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses or construction permits for pressurized
 
licenses or construction
 
permits for pressurized


water reactors (PWRs).
water reactors (PWRs).


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information


Commission (NRC) is issuing this information
notice to inform addressees that draft NUREG-1477, "Voltage-Based Interim


notice to inform addressees
Plugging Criteria for Steam Generator Tubes," is available for review and


that draft NUREG-1477, "Voltage-Based
comment. The draft report will be the basis for a final NUREG-1477 to be      outer


Interim Plugging Criteria for Steam Generator
issued on the use of voltage-based interim plugging criteria to address plate


Tubes," is available
diameter stress corrosion cracking (ODSCC)    at the  tube-to-tube support


for review and comment. The draft report will be the basis for a final NUREG-1477 to be issued on the use of voltage-based
NRC


interim plugging criteria to address outer diameter stress corrosion
intersections in steam generators. This information notice contains no


cracking (ODSCC) at the tube-to-tube
requirements, and no specific action    or written response  is required.


support plate intersections
Discussion


in steam generators.
a


This information
On July 2, 1993, the NRC published in the Federal Register (58 FR 35985)
notice that the above draft report  on  interim tube  plugging criteria  was


notice contains no NRC requirements, and no specific action or written response is required.Discussion
available for public comment. The conclusions and recommendations of theas


On July 2, 1993, the NRC published
draft report are preliminary and comments received will be incorporated            to


in the Federal Register (58 FR 35985) a notice that the above draft report on interim tube plugging criteria was available
applicable. The draft report was prepared by an NRC task group established


for public comment. The conclusions
review the technical bases for interim approval of voltage-based plugging


and recommendations
criteria for application to ODSCC, to review the outstanding issues associated


of the draft report are preliminary
with those criteria, and to prepare conclusions and recommendations for          most


and comments received will be incorporated
implementing those criteria. The report indicates that the NRC considers


as applicable.
of these issues to be relevant to the long-term approval of voltage-based


The draft report was prepared by an NRC task group established
plugging criteria. The task group was composed of NRC staff from the Offices


to review the technical
of Nuclear Reactor Regulation and Nuclear Regulatory Research, and consultants


bases for interim approval of voltage-based
from NRC contractors. The task group reviewed and evaluated tube integrity


plugging criteria for application
issues, including the potential for tube rupture or leakage under postulated


to ODSCC, to review the outstanding
accident conditions and their effect on safety. The task group also assessed


issues associated
outstanding technical issues and concerns that NRC staff members raised


with those criteria, and to prepare conclusions
regarding voltage-based plugging criteria for ODSCC.


and recommendations
The task group assessed tube integrity issues including (1) the ODSCC


for implementing
mechanism, (2) methods for evaluating margins against tube rupture and


those criteria.
estimating potential primary-to-secondary leakage, (3) operational primary-to-    In


The report indicates
secondary leakage limits, and (4) inservice inspection methods and scope.


that the NRC considers
9307080154                                M-O                        s:
                                                                      o~it-//e      ]\
                                                                                        VIv


most of these issues to be relevant to the long-term
._>./IN 93-52
                                                        \-
                                                                July 14, 1993 performing the assessment for item (2), the task group evaluated an NRC model


approval of voltage-based
and an industry model. The NRC model used a traditional mechanistic


plugging criteria.
approach for assessing tube integrity, while the industry model used an


The task group was composed of NRC staff from the Offices of Nuclear Reactor Regulation
empirical approach based on the voltage amplitude of eddy current


and Nuclear Regulatory
measurements. Analyses performed using these models predicted significantly


===Research, and consultants===
different primary-to-secondary leakage rates for postulated accident
from NRC contractors.


The task group reviewed and evaluated
conditions. Understanding and resolving this difference was important for the


tube integrity issues, including
task group to assess the safety implications with regard to offsite


the potential
radiological doses and core integrity.


for tube rupture or leakage under postulated
To determine the safety implications of the interim plugging criteria, the


accident conditions
task group performed calculations to assess the effect of a range of assumed


and their effect on safety. The task group also assessed outstanding
primary-to-secondary leak rates on radiological doses and the potential for


technical
core damage associated with them. The task group also performed a risk


issues and concerns that NRC staff members raised regarding
assessment to determine the safety significance of ODSCC of steam generator


voltage-based
tubes.


plugging criteria for ODSCC.The task group assessed tube integrity
The draft report documents the results of the task group effort including


issues including
preliminary conclusions and recommendations for implementing voltage-based


(1) the ODSCC mechanism, (2) methods for evaluating
interim plugging criteria. The draft report has been assigned NRC accession


margins against tube rupture and estimating
number 9306030163 and is available in the NRC public document rooms. The


potential
Federal Register notes that the NRC staff will consider all public comments on


primary-to-secondary
the draft report received within 45 days of the date of the Federal Register


leakage, (3) operational
notice and will revise the draft report as appropriate. The final report will


primary-to- secondary
be the technical basis for a forthcoming NRC staff generic position on the use


leakage limits, and (4) inservice
of voltage-based plugging criteria to address ODSCC at the tube-to-tube


inspection
support plate intersections. The NRC staff will prepare this generic position


methods and scope. In 9307080154 M-O s: VIv o~it-//e ]\
in accordance with applicable NRC procedures.
\- ._>./IN 93-52 July 14, 1993 performing


the assessment
If you wish to comment on the draft report, address your comments to the U.S.


for item (2), the task group evaluated
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.


an NRC model and an industry model. The NRC model used a traditional
20555. Comments should be provided within 45 days of the date of the


mechanistic
Federal Register notice to be considered in the revision to the report.


approach for assessing
IN 93-52 July 14, 1993 This information notice requires no specific action or written response. If


tube integrity, while the industry model used an empirical
you have any questions about the information in this notice, please contact


approach based on the voltage amplitude
one of the technical contacts listed below or the appropriate Office of


of eddy current measurements.
Nuclear Reactor Regulation (NRR) project manager.


Analyses performed
orig /s/'d by BKGrimes


using these models predicted
Brian K. Grimes, Director


significantly
Division of Operating Reactor Support


different
Office of Nuclear Reactor Regulation


primary-to-secondary
Technical contacts:      Jack Strosnider, NRR


leakage rates for postulated
(301) 504-2795 Richard Lobel, NRR


accident conditions.
(301) 504-2865 Attachment:


Understanding
===List of Recently Issued NRC Information Notices===
*SEE PREVIOUS CONCURRENCES


and resolving
OFFICE  TECH:ED*    DE:EMCB*    NRR:PD2-3*    DE:EMCB*    SCSB*
  NAME    JMain        EMurphy      TReed        JStrosnider  RLobel


this difference
DATE    06/18/93    06/25/93    07/01/93      07/01/93      06/24/93 OFFICE I D:DE*        }  OGCB:DORS*
                            JLBirmingham


was important
OGCB:DORS


for the task group to assess the safety implications
GMarcus*    B  me


with regard to offsite radiological
(
    NAME    JRichardson


doses and core integrity.
DATE  07/01/93        07/06/93        07/06/93    07/      1/93 OFFICIAL RECORD COPY


To determine
DOC NAME:    93-52.IN


the safety implications
IN 93-xx


of the interim plugging criteria, the task group performed
July x, 1993 This information notice requires no specific action or written response. If


calculations
you have any questions about the information in this notice, please contact


to assess the effect of a range of assumed primary-to-secondary
one of the technical contacts listed below or the appropriate Office of


leak rates on radiological
Nuclear Reactor Regulation (NRR) project manager.


doses and the potential
Brian K. Grimes, Director


for core damage associated
Division of Operating Reactor Support


with them. The task group also performed
Office of Nuclear Reactor Regulation


a risk assessment
Technical contacts:    Jack Strosnider, NRR


to determine
(301) 504-2795 Richard Lobel, NRR


the safety significance
(301) 504-2865 Attachments:  List of Recently Issued NRC Information Notices


of ODSCC of steam generator tubes.The draft report documents
*SEE PREVIOUS CONCURRENCES


the results of the task group effort including preliminary
OFFICE  TECH:ED*    DE:EMCB*    NRR:PD2-3*    DE:EMCB*      SCSB*
    AE  JMain      EMurphy    TReed        JStrosnider  RLobel


conclusions
DATE  06/18/93    06/25/93    07/01/93      07/01/93      06/24/93 OFFICE D:DE*    L    OGCB:DORS*        C :DORS    DDORS


and recommendations
NAE  JRichardson    JLBirmingham (GMarcus        BGrimes


for implementing
DATE  07/01/93      07/06/93        07/ b/93    07/  /93


voltage-based
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


interim plugging criteria.
IN 93-xx


The draft report has been assigned NRC accession number 9306030163 and is available
July x, 1993 This information notice requires no specific action or written response. If


in the NRC public document rooms. The Federal Register notes that the NRC staff will consider all public comments on the draft report received within 45 days of the date of the Federal Register notice and will revise the draft report as appropriate.
you have any questions about the information in this notice, please contact


The final report will be the technical
one of the technical contacts listed below or the appropriate Office of


basis for a forthcoming
Nuclear Reactor Regulation (NRR) project manager.


NRC staff generic position on the use of voltage-based
Brian K. Grimes, Director


plugging criteria to address ODSCC at the tube-to-tube
Division of Operating Reactor Support


support plate intersections.
Office of Nuclear Reactor Regulation


The NRC staff will prepare this generic position in accordance
Technical contacts:    Jack Strosnider, NRR


with applicable
(301) 504-2795 Richard Lobel, NRR


NRC procedures.
(301) 504-2865 Attachments:    List of Recently Issued NRC Information Notices


If you wish to comment on the draft report, address your comments to the U.S.Nuclear Regulatory
*SEE PREVIOUS CONCURRENCES


Commission, ATTN: Document Control Desk, Washington, D.C.20555. Comments should be provided within 45 days of the date of the Federal Register notice to be considered
OFFICE TECH:ED    DE:EMCB    NRR:PD2-3      DE:EMCB      SCSB


in the revision to the report.
MME  JMain*      EMurphy*    TReed*        JStrosnider  RLobel*
  DATE  06/18/93    06/25/93    07/01/93      07/01/93      06/24/93
[OFFICE  D:DE          OGCB:DORS4y61 OGCB:DORS      [D:DORS


IN 93-52 July 14, 1993 This information
NAME  JRichardson  JLBirmingham    GMarcus      BGrimes


notice requires no specific action or written response.
DATE  07/01/93      07/___93      l07/    /93    07/ /93


If you have any questions
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


about the information
IN 93-xx


in this notice, please contact one of the technical
July x, 1993 This information notice requires no specific action or written response. If


contacts listed below or the appropriate
you have any questions about the information in this notice, please contact


Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating
one of the technical contacts listed below or the appropriate Office of


===Reactor Support Office of Nuclear Reactor Regulation===
Nuclear Reactor Regulation (NRR) project manager.
Technical


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachment:
Brian K. Grimes, Director
List of Recently Issued NRC Information


Notices*SEE PREVIOUS CONCURRENCES
Division of Operating Reactor Support


OFFICE TECH:ED* DE:EMCB* NRR:PD2-3*
Office of Nuclear Reactor Regulation
DE:EMCB* SCSB*NAME JMain EMurphy TReed JStrosnider


RLobel DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93 OFFICE I D:DE* } OGCB:DORS*
Technical contacts:       Jack Strosnider, NRR
OGCB:DORS NAME JRichardson


JLBirmingham
(301) 504-2795 Richard Lobel, NRR


GMarcus* B me DATE 07/01/93 07/06/93 07/06/93 07/ 1/93 (OFFICIAL RECORD COPY DOC NAME: 93-52.IN
(301) 504-2865 Attachment:     List of Recently Issued NRC Information Notices


IN 93-xx July x, 1993 This information
*SEE PREVIOUS CONCURRENCES


notice requires no specific action or written response.
OFFICE  TECH:ED      DE:EMCB      NRR:PD2-3        E: EMCB /    SCSB


If you have any questions
MME    JMain*        EMurphy*    TReed        6Strosnider      RLobel*
  DATE  06/18/93      06/25/93    06/  /93      O/ / /93      06/24/93 OFFICE  D: RE            OGCB:DORS        OGCB:DORS      D:DORS


about the information
"AME h i r dson        JLBirmingham      GMarcus        BGrimes


in this notice, please contact one of the technical
__DATE _  __0_7_/___
            __/1/93          _  9_3
                                _<__        07/  /93      07/  /93


contacts listed below or the appropriate
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
IN 93-xx


===Reactor Support Office of Nuclear Reactor Regulation===
July x, 1993 This information notice requires no specific action or written response. If
Technical


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
you have any questions about the information in this notice, please contact
List of Recently Issued NRC Information


Notices*SEE PREVIOUS CONCURRENCES
one of the technical contacts listed below or the appropriate Office of


OFFICE TECH:ED* DE:EMCB* NRR:PD2-3*
Nuclear Reactor Regulation (NRR) project manager.
DE:EMCB* SCSB*AE JMain EMurphy TReed JStrosnider


RLobel DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93 OFFICE D:DE* L OGCB:DORS*
Brian K. Grimes, Director
C :DORS DDORS NAE JRichardson


JLBirmingham (GMarcus BGrimes DATE 07/01/93 07/06/93 07/ b/93 07/ /93 OFFICIAL RECORD COPY FILENAME:
Division of Operating Reactor Support
NUREG.IN


IN 93-xx July x, 1993 This information
Office of Nuclear Reactor Regulation


notice requires no specific action or written response.
Technical contacts:      Jack Strosnider, NRR


If you have any questions
(301) 504-2795 Richard Lobel, NRR


about the information
(301) 504-2865 Attachments:
1. Draft NUREG-1477, "Voltage-Based Interim Plugging


in this notice, please contact one of the technical
Criteria for Steam Generator Tubes"
2. List of Recently Issued NRC Information Notices


contacts listed below or the appropriate
*SEE PREVIOUS CONCURRENCES


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
OFFICE    TECH:ED    DE:EMCB      NRR:PD2-3      9E:EMCB #      SCSB


===Reactor Support Office of Nuclear Reactor Regulation===
NAE      JMain*      EMurphy*    TReed    '    t  osnider    RLobel*
Technical
  DATE    06/18/93  06/25/93    j06/  /93            9/3    06/24/93 OFFICEj  D:DE          OGCB:DORS        OGCB:DORS    D:DORS


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
E    JRichardson    JLBirmingham    GMarcus      BGrimes
List of Recently Issued NRC Information


Notices*SEE PREVIOUS CONCURRENCES
DATE    06/  /93    j07/  /93      107/  /93    07/  /93  J


OFFICE TECH:ED DE:EMCB NRR:PD2-3 DE:EMCB SCSB MME JMain* EMurphy* TReed* JStrosnider
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


RLobel*DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93[OFFICE D:DE OGCB:DORS4y6
IN 93-xx
1 OGCB:DORS


[D:DORS NAME JRichardson
July x, 1993 This information notice requires no specific action or written response. If


JLBirmingham
you have any questions about the information in this notice, please contact


GMarcus BGrimes DATE 07/01/93 07/___93 l 07/ /93 07/ /93 OFFICIAL RECORD COPY FILENAME:
one of the technical contacts listed below or the appropriate Office of
NUREG.IN


IN 93-xx July x, 1993 This information
Nuclear Reactor Regulation (NRR) project manager.


notice requires no specific action or written response.
Brian K. Grimes, Director


If you have any questions
Division of Operating Reactor Support


about the information
Office of Nuclear Reactor Regulation


in this notice, please contact one of the technical
Technical contacts:    Jack Strosnider, NRR


contacts listed below or the appropriate
(301) 504-2795 Richard Lobel, NRR


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
(301) 504-2865 Attachments:
1. Draft NUREG-1477, Voltage-Based Interim Plugging


===Reactor Support Office of Nuclear Reactor Regulation===
Criteria for Steam Generator Tubes"
Technical
2. List of Recently Issued NRC Information Notices


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachment:
*SEE PREVIOUS CONCURRENCES
List of Recently Issued NRC Information


Notices*SEE PREVIOUS CONCURRENCES
OFFICE  TECH:ED    DE:EMCB      NRR:PD2-      DE:EMCB      SCSB


OFFICE TECH:ED DE:EMCB NRR:PD2-3 E: EMCB / SCSB MME JMain* EMurphy* TReed 6Strosnider
OAE    JMain*      EMurphy*    TReed f        JStrosnider  RLobel*
  DATE    06/18/93    06/25/93    2/i9            06/  /93      06/24/93 OFFIC    D:DE         OGCB:DORS          OGCB:DORS    D:DORS


RLobel*DATE 06/18/93 06/25/93 06/ /93 O/ / /93 06/24/93 OFFICE D: RE OGCB:DORS
KlME    JRichardson  JLBirmingham      GMarcus      BGrimes


OGCB:DORS
DATE    06/ /93      07/  /93        107/  /93    07/  /93


D:DORS"AME h i r dson JLBirmingham
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


GMarcus BGrimes__ DATE _ __/1/93 __0_7_/___
IN 93-XX
9_ 3 _ _<__ 07/ /93 07/ /93 OFFICIAL RECORD COPY FILENAME:
NUREG.IN


IN 93-xx July x, 1993 This information
July xx, 1993 This information notice requires no specific action or written response. If


notice requires no specific action or written response.
you have any questions about the information in this notice, please contact


If you have any questions
one of the technical contacts listed below or the appropriate Office of


about the information
Nuclear Reactor Regulation (NRR) project manager.


in this notice, please contact one of the technical
Brian K. Grimes, Director


contacts listed below or the appropriate
Division of Operating Reactor Support


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Office of Nuclear Reactor Regulation


===Reactor Support Office of Nuclear Reactor Regulation===
Technical contacts:      Jack Strosnider, NRR
Technical


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
(301) 504-2795 Richard Lobel, NRR
1. Draft NUREG-1477, "Voltage-Based


Interim Plugging Criteria for Steam Generator
(301) 504-2865 Attachments:
1. Draft NUREG-1477, "Voltage-Based Interim Plugging


Tubes" 2. List of Recently Issued NRC Information
Criteria for Steam Generator Tubes - Task Group Report"
2. List of Recently Issued NRC information Notices


Notices*SEE PREVIOUS CONCURRENCES
*SEE PREVIOUS CONCURRENCE


OFFICE TECH:ED DE:EMCB NRR:PD2-3  
OFFICE I TECH                     NRR:PD2-3     DE:EMCB       SCSB
9E:EMCB # SCSB NAE JMain* EMurphy* TReed ' t osnider RLobel*DATE 06/18/93 06/25/93 j06/ /93 9/3 06/24/93 OFFICEj D:DE OGCB:DORS


OGCB:DORS
NAME        jetphy              TReed        JStrosnider    RLobel*
 
  DATE    06/1d/93    06/A493    06/ /93      06/ /93        06/ /93 OFFICE    D:DE          OGCB:DORS      C/OGCB:DORS   D:DORS
D:DORS E JRichardson


JLBirmingham
NAME    JRichardson  JLBirmingham   GMarcus        BGrimes


GMarcus BGrimes DATE 06/ /93 j07/ /93 1 07/ /93 07/ /93 J OFFICIAL RECORD COPY FILENAME:
DATE     06/ /93       06/ /93         0 / /93       0 / /93J
NUREG.IN


IN 93-xx July x, 1993 This information
OFFICIAL RECORD COPY


notice requires no specific action or written response.
FILENAME: NUREG.IN


If you have any questions
'-
This information notice requires no specific action or written response. If


about the information
you have any questions about the information in this notice, please contact


in this notice, please contact one of the technical
one of the technical contacts listed below or the appropriate Office of


contacts listed below or the appropriate
Nuclear Reactor Regulation (NRR) project manager.


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Brian K. Grimes, Director


===Reactor Support Office of Nuclear Reactor Regulation===
Division of Operating Reactor Support
Technical


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
Office of Nuclear Reactor Regulation
1. Draft NUREG-1477, Voltage-Based


Interim Plugging Criteria for Steam Generator
Technical contacts:      Jack Strosnider, NRR


Tubes" 2. List of Recently Issued NRC Information
(301) 504-2795 Richard Lobel, NRR


Notices*SEE PREVIOUS CONCURRENCES
(301) 504-2865 Attachments:
1. Draft report, "Voltage-Based Interim Plugging


OFFICE TECH:ED DE:EMCB NRR:PD2- DE:EMCB SCSB OAE JMain* EMurphy* TReed f JStrosnider
Criteria for Steam Generator Tubes - Task Group Report"
2. List of Recently Issued NRC information Notices


RLobel*DATE 06/18/93 06/25/93 2/i9 06/ /93 06/24/93 OFFIC D:DE OGCB:DORS
OFFICE    DE:EMCB    NRR:PD2-3    DE:EMCB        SCSB


OGCB:DORS
"ME    IEMurphy    TReed        JStrosnider    RLobel


D:DORS KlME JRichardson
DATE      6/ /93  . 6/ /93        6/ /93 OFFICE    D:DE          OGCB:DORS      C/OGCB:DORS    D:DORS


JLBirmingham
iME    JRichardson    JLBirmingham   GMarcus        BGrimes


GMarcus BGrimes DATE 06/ /93 07/ /93 107/ /93 07/ /93 OFFICIAL RECORD COPY FILENAME:
DATE     6/ /93     16/   /93         / /93         / /93 J
NUREG.IN


IN 93-XX July xx, 1993 This information
===OFFICIAL RECORD COPY===
FILENAME: NUREG.IN


notice requires no specific action or written response.
IN 93-52 July 14, 1993 If


If you have any questions
This information notice requires no specific action or written response.


about the information
contact


in this notice, please contact one of the technical
you have any questions about the information in this notice, please


contacts listed below or the appropriate
one of the technical contacts listed below or the appropriate Office of


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Nuclear Reactor Regulation (NRR) project manager.


===Reactor Support Office of Nuclear Reactor Regulation===
Brian K. Grimes, Director
Technical


contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
Division of Operating Reactor Support
1. Draft NUREG-1477, "Voltage-Based


Interim Plugging Criteria for Steam Generator
Office of Nuclear Reactor Regulation


Tubes -Task Group Report" 2. List of Recently Issued NRC information
Technical contacts:  Jack Strosnider, NRR


Notices*SEE PREVIOUS CONCURRENCE
(301) 504-2795 Richard Lobel, NRR


OFFICE I TECH NRR:PD2-3 DE:EMCB SCSB NAME jetphy TReed JStrosnider
(301) 504-2865 Attachment:
List of Recently Issued NRC Information Notices


RLobel*DATE 06/1d/93 06/A493 06/ /93 06/ /93 06/ /93 OFFICE D:DE OGCB:DORS
A'tachment


C/OGCB:DORS
IN 93-52 July 14, 1993 LIST OF RECENTLY ISSUED


D:DORS NAME JRichardson
NRC INFORMATION NOTICES


JLBirmingham
Information                                    Date of


GMarcus BGrimes DATE 06/ /93 06/ /93 0 / /93 0 / /93J OFFICIAL RECORD COPY FILENAME:
Notice No.             Subject                  Issuance  Issued to
NUREG.IN


' -This information
93-51          Repetitive Overspeed            07/09/93  All holders of OLs or CPs


notice requires no specific action or written response.
Tripping of Turbine-                        for nuclear power reactors.


If you have any questions
Driven Auxiliary Feed- water Pumps


about the information
93-50          Extended Storage of              07/08/93  All licensees authorized


in this notice, please contact one of the technical
Sealed Sources                              to possess sealed sources.
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
 
===Reactor Support Office of Nuclear Reactor Regulation===
Technical
 
contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachments:
1. Draft report, "Voltage-Based
 
Interim Plugging Criteria for Steam Generator
 
Tubes -Task Group Report" 2. List of Recently Issued NRC information
 
Notices OFFICE DE:EMCB NRR:PD2-3 DE:EMCB SCSB"ME IEMurphy TReed JStrosnider
 
RLobel DATE 6/ /93 .6/ /93 6/ /93 OFFICE D:DE OGCB:DORS
 
C/OGCB:DORS
 
D:DORS iME JRichardson
 
JLBirmingham
 
GMarcus BGrimes DATE 6/ /93 16/ /93 / /93 / /93 J OFFICIAL RECORD COPY FILENAME:
NUREG.IN
 
IN 93-52 July 14, 1993 This information
 
notice requires no specific action or written response.
 
If you have any questions
 
about the information
 
in this notice, please contact one of the technical
 
contacts listed below or the appropriate
 
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
 
===Reactor Support Office of Nuclear Reactor Regulation===
Technical
 
contacts: Jack Strosnider, NRR (301) 504-2795 Richard Lobel, NRR (301) 504-2865 Attachment:
List of Recently Issued NRC Information
 
Notices
 
A'tachment


IN 93-52 July 14, 1993 LIST OF RECENTLY ISSUED NRC INFORMATION
93-49          Improper Integration of        07/08/93    All holders of OLs or CPs


NOTICES Information
Software into Operating                    for nuclear power reactors.


Date of Notice No. Subject Issuance Issued to 93-51 93-50 93-49 93-48 92-06, Supp. 1 93-47 93-46 93-45 93-44 Repetitive
Practices


Overspeed Tripping of Turbine-Driven Auxiliary
93-48          Failure of Turbine-             7/6/93    All holders of OLs or CPs


Feed-water Pumps Extended Storage of Sealed Sources Improper Integration
Driven Main Feedwater                      for nuclear power reactors.


of Software into Operating Practices Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated
Pump to Trip Because of


Oil Reliability
Contaminated Oil


of ATWS Mitigation
92-06,          Reliability of ATWS             07/01/93  All holders of OLs or CPs


Systems and Other NRC-Required
Supp. 1        Mitigation Systems and                     for nuclear power reactors.


Equip-ment not Controlled
Other NRC-Required Equip- ment not Controlled by


by Plant Technical
Plant Technical Specifica- tion


Specifica- tion Unrecognized
93-47          Unrecognized Loss of            06/18/93  All holders of OLs or CPs


===Loss of Control Room Annunciators===
Control Room Annunciators                   for nuclear power reactors.
Potential


Problem with Westinghouse
93-46          Potential Problem with           6/10/93    All holders of OLs or CPs


===Rod Control System and Inadvertent===
Westinghouse  Rod Control                   for Westinghouse (W)-
Withdrawal
                System and Inadvertent                     designed nuclear power


of A Single Rod Control Cluster Assembly Degradation
Withdrawal of A Single                       reactors.


of Shutdown Cooling System Performance
Rod Control Cluster Assembly


Operational
93-45          Degradation of Shutdown        06/16/93    All holders of OLs or CPs


Challenges
Cooling System Performance                  for nuclear power reactors.


During A Dual-Unit Transient 07/09/93 07/08/93 07/08/93 7/6/93 07/01/93 06/18/93 6/10/93 06/16/93 06/15/93 All holders of OLs or CPs for nuclear power reactors.All licensees
93-44          Operational Challenges          06/15/93   All holders of OLs or CPs


authorized
During A Dual-Unit                          for nuclear power reactors.


to possess sealed sources.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for Westinghouse (W)-designed nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.OL = Operating
Transient


License CP = Construction
OL = Operating License


Permit}}
CP = Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:21, 24 November 2019

Draft NUREG-1477, Voltage-Based Interim Plugging Criteria for Stem Generator Tubes.
ML031070370
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 07/14/1993
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
NUREG-1477 IN-93-052, NUDOCS 9307080154
Download: ML031070370 (12)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 July 14, 1993 NRC INFORMATION NOTICE 93-52: DRAFT NUREG-1477, "VOLTAGE-BASED INTERIM

PLUGGING CRITERIA FOR STEAM GENERATOR TUBES"

Addressees

All holders of operating licenses or construction permits for pressurized

water reactors (PWRs).

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to inform addressees that draft NUREG-1477, "Voltage-Based Interim

Plugging Criteria for Steam Generator Tubes," is available for review and

comment. The draft report will be the basis for a final NUREG-1477 to be outer

issued on the use of voltage-based interim plugging criteria to address plate

diameter stress corrosion cracking (ODSCC) at the tube-to-tube support

NRC

intersections in steam generators. This information notice contains no

requirements, and no specific action or written response is required.

Discussion

a

On July 2, 1993, the NRC published in the Federal Register (58 FR 35985)

notice that the above draft report on interim tube plugging criteria was

available for public comment. The conclusions and recommendations of theas

draft report are preliminary and comments received will be incorporated to

applicable. The draft report was prepared by an NRC task group established

review the technical bases for interim approval of voltage-based plugging

criteria for application to ODSCC, to review the outstanding issues associated

with those criteria, and to prepare conclusions and recommendations for most

implementing those criteria. The report indicates that the NRC considers

of these issues to be relevant to the long-term approval of voltage-based

plugging criteria. The task group was composed of NRC staff from the Offices

of Nuclear Reactor Regulation and Nuclear Regulatory Research, and consultants

from NRC contractors. The task group reviewed and evaluated tube integrity

issues, including the potential for tube rupture or leakage under postulated

accident conditions and their effect on safety. The task group also assessed

outstanding technical issues and concerns that NRC staff members raised

regarding voltage-based plugging criteria for ODSCC.

The task group assessed tube integrity issues including (1) the ODSCC

mechanism, (2) methods for evaluating margins against tube rupture and

estimating potential primary-to-secondary leakage, (3) operational primary-to- In

secondary leakage limits, and (4) inservice inspection methods and scope.

9307080154 M-O s:

o~it-//e ]\

VIv

._>./IN 93-52

\-

July 14, 1993 performing the assessment for item (2), the task group evaluated an NRC model

and an industry model. The NRC model used a traditional mechanistic

approach for assessing tube integrity, while the industry model used an

empirical approach based on the voltage amplitude of eddy current

measurements. Analyses performed using these models predicted significantly

different primary-to-secondary leakage rates for postulated accident

conditions. Understanding and resolving this difference was important for the

task group to assess the safety implications with regard to offsite

radiological doses and core integrity.

To determine the safety implications of the interim plugging criteria, the

task group performed calculations to assess the effect of a range of assumed

primary-to-secondary leak rates on radiological doses and the potential for

core damage associated with them. The task group also performed a risk

assessment to determine the safety significance of ODSCC of steam generator

tubes.

The draft report documents the results of the task group effort including

preliminary conclusions and recommendations for implementing voltage-based

interim plugging criteria. The draft report has been assigned NRC accession

number 9306030163 and is available in the NRC public document rooms. The

Federal Register notes that the NRC staff will consider all public comments on

the draft report received within 45 days of the date of the Federal Register

notice and will revise the draft report as appropriate. The final report will

be the technical basis for a forthcoming NRC staff generic position on the use

of voltage-based plugging criteria to address ODSCC at the tube-to-tube

support plate intersections. The NRC staff will prepare this generic position

in accordance with applicable NRC procedures.

If you wish to comment on the draft report, address your comments to the U.S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.

20555. Comments should be provided within 45 days of the date of the

Federal Register notice to be considered in the revision to the report.

IN 93-52 July 14, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

orig /s/'d by BKGrimes

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED* DE:EMCB* NRR:PD2-3* DE:EMCB* SCSB*

NAME JMain EMurphy TReed JStrosnider RLobel

DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93 OFFICE I D:DE* } OGCB:DORS*

JLBirmingham

OGCB:DORS

GMarcus* B me

(

NAME JRichardson

DATE 07/01/93 07/06/93 07/06/93 07/ 1/93 OFFICIAL RECORD COPY

DOC NAME: 93-52.IN

IN 93-xx

July x, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED* DE:EMCB* NRR:PD2-3* DE:EMCB* SCSB*

AE JMain EMurphy TReed JStrosnider RLobel

DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93 OFFICE D:DE* L OGCB:DORS* C :DORS DDORS

NAE JRichardson JLBirmingham (GMarcus BGrimes

DATE 07/01/93 07/06/93 07/ b/93 07/ /93

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-xx

July x, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED DE:EMCB NRR:PD2-3 DE:EMCB SCSB

MME JMain* EMurphy* TReed* JStrosnider RLobel*

DATE 06/18/93 06/25/93 07/01/93 07/01/93 06/24/93

[OFFICE D:DE OGCB:DORS4y61 OGCB:DORS [D:DORS

NAME JRichardson JLBirmingham GMarcus BGrimes

DATE 07/01/93 07/___93 l07/ /93 07/ /93

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-xx

July x, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED DE:EMCB NRR:PD2-3 E: EMCB / SCSB

MME JMain* EMurphy* TReed 6Strosnider RLobel*

DATE 06/18/93 06/25/93 06/ /93 O/ / /93 06/24/93 OFFICE D: RE OGCB:DORS OGCB:DORS D:DORS

"AME h i r dson JLBirmingham GMarcus BGrimes

__DATE _ __0_7_/___

__/1/93 _ 9_3

_<__ 07/ /93 07/ /93

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-xx

July x, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments:

1. Draft NUREG-1477, "Voltage-Based Interim Plugging

Criteria for Steam Generator Tubes"

2. List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED DE:EMCB NRR:PD2-3 9E:EMCB # SCSB

NAE JMain* EMurphy* TReed ' t osnider RLobel*

DATE 06/18/93 06/25/93 j06/ /93 9/3 06/24/93 OFFICEj D:DE OGCB:DORS OGCB:DORS D:DORS

E JRichardson JLBirmingham GMarcus BGrimes

DATE 06/ /93 j07/ /93 107/ /93 07/ /93 J

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-xx

July x, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments:

1. Draft NUREG-1477, Voltage-Based Interim Plugging

Criteria for Steam Generator Tubes"

2. List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

OFFICE TECH:ED DE:EMCB NRR:PD2- DE:EMCB SCSB

OAE JMain* EMurphy* TReed f JStrosnider RLobel*

DATE 06/18/93 06/25/93 2/i9 06/ /93 06/24/93 OFFIC D:DE OGCB:DORS OGCB:DORS D:DORS

KlME JRichardson JLBirmingham GMarcus BGrimes

DATE 06/ /93 07/ /93 107/ /93 07/ /93

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-XX

July xx, 1993 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments:

1. Draft NUREG-1477, "Voltage-Based Interim Plugging

Criteria for Steam Generator Tubes - Task Group Report"

2. List of Recently Issued NRC information Notices

  • SEE PREVIOUS CONCURRENCE

OFFICE I TECH NRR:PD2-3 DE:EMCB SCSB

NAME jetphy TReed JStrosnider RLobel*

DATE 06/1d/93 06/A493 06/ /93 06/ /93 06/ /93 OFFICE D:DE OGCB:DORS C/OGCB:DORS D:DORS

NAME JRichardson JLBirmingham GMarcus BGrimes

DATE 06/ /93 06/ /93 0 / /93 0 / /93J

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

'-

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachments:

1. Draft report, "Voltage-Based Interim Plugging

Criteria for Steam Generator Tubes - Task Group Report"

2. List of Recently Issued NRC information Notices

OFFICE DE:EMCB NRR:PD2-3 DE:EMCB SCSB

"ME IEMurphy TReed JStrosnider RLobel

DATE 6/ /93 . 6/ /93 6/ /93 OFFICE D:DE OGCB:DORS C/OGCB:DORS D:DORS

iME JRichardson JLBirmingham GMarcus BGrimes

DATE 6/ /93 16/ /93 / /93 / /93 J

OFFICIAL RECORD COPY

FILENAME: NUREG.IN

IN 93-52 July 14, 1993 If

This information notice requires no specific action or written response.

contact

you have any questions about the information in this notice, please

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Jack Strosnider, NRR

(301) 504-2795 Richard Lobel, NRR

(301) 504-2865 Attachment:

List of Recently Issued NRC Information Notices

A'tachment

IN 93-52 July 14, 1993 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

93-51 Repetitive Overspeed 07/09/93 All holders of OLs or CPs

Tripping of Turbine- for nuclear power reactors.

Driven Auxiliary Feed- water Pumps

93-50 Extended Storage of 07/08/93 All licensees authorized

Sealed Sources to possess sealed sources.

93-49 Improper Integration of 07/08/93 All holders of OLs or CPs

Software into Operating for nuclear power reactors.

Practices

93-48 Failure of Turbine- 7/6/93 All holders of OLs or CPs

Driven Main Feedwater for nuclear power reactors.

Pump to Trip Because of

Contaminated Oil

92-06, Reliability of ATWS 07/01/93 All holders of OLs or CPs

Supp. 1 Mitigation Systems and for nuclear power reactors.

Other NRC-Required Equip- ment not Controlled by

Plant Technical Specifica- tion

93-47 Unrecognized Loss of 06/18/93 All holders of OLs or CPs

Control Room Annunciators for nuclear power reactors.

93-46 Potential Problem with 6/10/93 All holders of OLs or CPs

Westinghouse Rod Control for Westinghouse (W)-

System and Inadvertent designed nuclear power

Withdrawal of A Single reactors.

Rod Control Cluster Assembly

93-45 Degradation of Shutdown 06/16/93 All holders of OLs or CPs

Cooling System Performance for nuclear power reactors.

93-44 Operational Challenges 06/15/93 All holders of OLs or CPs

During A Dual-Unit for nuclear power reactors.

Transient

OL = Operating License

CP = Construction Permit


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