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 =  
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| page count = 12
| page count = 12
}}
}}
{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555July 14, 1993NRC INFORMATION NOTICE 93-52: DRAFT NUREG-1477, "VOLTAGE-BASED INTERIMPLUGGING CRITERIA FOR STEAM GENERATOR TUBES"
{{#Wiki_filter: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==
==Addressees==
All holders of operating licenses or construction permits for pressurizedwater reactors (PWRs).
All holders of operating licenses or construction permits for pressurized
 
water reactors (PWRs).


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to inform addressees that draft NUREG-1477, "Voltage-Based InterimPlugging Criteria for Steam Generator Tubes," is available for review andcomment. The draft report will be the basis for a final NUREG-1477 to beissued on the use of voltage-based interim plugging criteria to address outerdiameter stress corrosion cracking (ODSCC) at the tube-to-tube support plateintersections in steam generators. This information notice contains no NRCrequirements, and no specific action or written response is required.DiscussionOn July 2, 1993, the NRC published in the Federal Register (58 FR 35985) anotice that the above draft report on interim tube plugging criteria wasavailable for public comment. The conclusions and recommendations of thedraft report are preliminary and comments received will be incorporated asapplicable. The draft report was prepared by an NRC task group established toreview the technical bases for interim approval of voltage-based pluggingcriteria for application to ODSCC, to review the outstanding issues associatedwith those criteria, and to prepare conclusions and recommendations forimplementing those criteria. The report indicates that the NRC considers mostof these issues to be relevant to the long-term approval of voltage-basedplugging criteria. The task group was composed of NRC staff from the Officesof Nuclear Reactor Regulation and Nuclear Regulatory Research, and consultantsfrom NRC contractors. The task group reviewed and evaluated tube integrityissues, including the potential for tube rupture or leakage under postulatedaccident conditions and their effect on safety. The task group also assessedoutstanding technical issues and concerns that NRC staff members raisedregarding voltage-based plugging criteria for ODSCC.The task group assessed tube integrity issues including (1) the ODSCCmechanism, (2) methods for evaluating margins against tube rupture andestimating potential primary-to-secondary leakage, (3) operational primary-to-secondary leakage limits, and (4) inservice inspection methods and scope. In9307080154 M-O s:VIvo~it-//e ]\  
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
\- ._>./IN 93-52July 14, 1993 performing the assessment for item (2), the task group evaluated an NRC modeland an industry model. The NRC model used a traditional mechanisticapproach for assessing tube integrity, while the industry model used anempirical approach based on the voltage amplitude of eddy currentmeasurements. Analyses performed using these models predicted significantlydifferent primary-to-secondary leakage rates for postulated accidentconditions. Understanding and resolving this difference was important for thetask group to assess the safety implications with regard to offsiteradiological doses and core integrity.To determine the safety implications of the interim plugging criteria, thetask group performed calculations to assess the effect of a range of assumedprimary-to-secondary leak rates on radiological doses and the potential forcore damage associated with them. The task group also performed a riskassessment to determine the safety significance of ODSCC of steam generatortubes.The draft report documents the results of the task group effort includingpreliminary conclusions and recommendations for implementing voltage-basedinterim plugging criteria. The draft report has been assigned NRC accessionnumber 9306030163 and is available in the NRC public document rooms. TheFederal Register notes that the NRC staff will consider all public comments onthe draft report received within 45 days of the date of the Federal Registernotice and will revise the draft report as appropriate. The final report willbe the technical basis for a forthcoming NRC staff generic position on the useof voltage-based plugging criteria to address ODSCC at the tube-to-tubesupport plate intersections. The NRC staff will prepare this generic positionin 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 theFederal Register notice to be considered in the revision to the report.
 
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


IN 93-52July 14, 1993 DOC NAME: 93-52.IN
Technical contacts:      Jack Strosnider, NRR


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
(301) 504-2795 Richard Lobel, NRR


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
(301) 504-2865 Attachments:
1. Draft report, "Voltage-Based Interim Plugging


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
Criteria for Steam Generator Tubes - Task Group Report"
2. List of Recently Issued NRC information Notices


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
OFFICE    DE:EMCB    NRR:PD2-3    DE:EMCB        SCSB


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
"ME    IEMurphy    TReed        JStrosnider    RLobel


IN 93-XXJuly xx, 1993 FILENAME: NUREG.IN
DATE      6/ /93 . 6/ /93        6/ /93 OFFICE    D:DE          OGCB:DORS      C/OGCB:DORS    D:DORS


' -This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Jack Strosnider, NRR(301) 504-2795Richard Lobel, NRR(301) 504-2865Attachments:1. Draft report, "Voltage-Based Interim PluggingCriteria for Steam Generator Tubes -Task Group Report"2. List of Recently Issued NRC information NoticesOFFICE DE:EMCB NRR:PD2-3 DE:EMCB SCSB"ME IEMurphy TReed JStrosnider RLobelDATE 6/ /93 .6/ /93 6/ /93OFFICE D:DE OGCB:DORS C/OGCB:DORS D:DORSiME JRichardson JLBirmingham GMarcus BGrimesDATE 6/ /93 16/ /93 / /93 / /93 JOFFICIAL RECORD COPYFILENAME: NUREG.IN
iME    JRichardson   JLBirmingham   GMarcus       BGrimes


IN 93-52July 14, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Jack Strosnider, NRR(301) 504-2795Richard Lobel, NRR(301) 504-2865Attachment:List of Recently Issued NRC Information Notices
DATE      6/ /93     16/    /93          / /93          / /93 J


A'tachmentIN 93-52July 14, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-5193-5093-4993-4892-06,Supp. 193-4793-4693-4593-44Repetitive OverspeedTripping of Turbine-Driven Auxiliary Feed-water PumpsExtended Storage ofSealed SourcesImproper Integration ofSoftware into OperatingPracticesFailure of Turbine-Driven Main FeedwaterPump to Trip Because ofContaminated OilReliability of ATWSMitigation Systems andOther NRC-Required Equip-ment not Controlled byPlant Technical Specifica-tionUnrecognized Loss ofControl Room AnnunciatorsPotential Problem withWestinghouse Rod ControlSystem and InadvertentWithdrawal of A SingleRod Control Cluster AssemblyDegradation of ShutdownCooling System PerformanceOperational ChallengesDuring A Dual-UnitTransient07/09/9307/08/9307/08/937/6/9307/01/9306/18/936/10/9306/16/9306/15/93All holders of OLs or CPsfor nuclear power reactors.All licensees authorizedto possess sealed sources.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor Westinghouse (W)-designed nuclear powerreactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.OL = Operating LicenseCP = Construction Permit
===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}}


{{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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