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

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{{#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
\- ._>./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.
 
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 issued on the use of voltage-based
 
interim plugging criteria to address outer diameter stress corrosion
 
cracking (ODSCC) at the tube-to-tube
 
support plate intersections
 
in steam generators.
 
This information
 
notice contains no NRC requirements, and no specific action or written response is required.Discussion
 
On July 2, 1993, the NRC published
 
in the Federal Register (58 FR 35985) a notice that the above draft report on interim tube plugging criteria was available
 
for public comment. The conclusions
 
and recommendations
 
of the draft report are preliminary
 
and comments received will be incorporated
 
as applicable.
 
The draft report was prepared by an NRC task group established
 
to 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 implementing
 
those criteria.
 
The report indicates
 
that the NRC considers
 
most 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- secondary
 
leakage limits, and (4) inservice
 
inspection
 
methods and scope. In 9307080154 M-O s: VIv o~it-//e ]\  
\- ._>./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*
OGCB:DORS NAME JRichardson
 
JLBirmingham
 
GMarcus* B me 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:DORS4y6
1 OGCB:DORS
 
[D:DORS NAME JRichardson
 
JLBirmingham
 
GMarcus BGrimes DATE 07/01/93 07/___93 l 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 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 _ __/1/93 __0_7_/___
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 1 07/ /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 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
 
NOTICES Information
 
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
 
Overspeed Tripping of Turbine-Driven Auxiliary
 
Feed-water Pumps Extended Storage of Sealed Sources Improper Integration
 
of Software into Operating Practices Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated
 
Oil Reliability
 
of ATWS Mitigation
 
Systems and Other NRC-Required
 
Equip-ment not Controlled
 
by Plant Technical
 
Specifica- tion Unrecognized
 
===Loss of Control Room Annunciators===
Potential


IN 93-52July 14, 1993 DOC NAME: 93-52.IN
Problem with Westinghouse


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
===Rod Control System and Inadvertent===
Withdrawal


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
of A Single Rod Control Cluster Assembly Degradation


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
of Shutdown Cooling System Performance


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
Operational


IN 93-xxJuly x, 1993 FILENAME: NUREG.IN
Challenges


IN 93-XXJuly xx, 1993 FILENAME: NUREG.IN
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


' -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
authorized


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
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


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
License CP = Construction


}}
Permit}}


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

Revision as of 13:54, 31 August 2018

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 K
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 issued on the use of voltage-based

interim plugging criteria to address outer diameter stress corrosion

cracking (ODSCC) at the tube-to-tube

support plate intersections

in steam generators.

This information

notice contains no NRC requirements, and no specific action or written response is required.Discussion

On July 2, 1993, the NRC published

in the Federal Register (58 FR 35985) a notice that the above draft report on interim tube plugging criteria was available

for public comment. The conclusions

and recommendations

of the draft report are preliminary

and comments received will be incorporated

as applicable.

The draft report was prepared by an NRC task group established

to 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 implementing

those criteria.

The report indicates

that the NRC considers

most 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- secondary

leakage limits, and (4) inservice

inspection

methods and scope. In 9307080154 M-O s: VIv o~it-//e ]\

\- ._>./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*

OGCB:DORS NAME JRichardson

JLBirmingham

GMarcus* B me 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:DORS4y6

1 OGCB:DORS

[D:DORS NAME JRichardson

JLBirmingham

GMarcus BGrimes DATE 07/01/93 07/___93 l 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 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 _ __/1/93 __0_7_/___

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 1 07/ /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 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

NOTICES Information

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

Overspeed Tripping of Turbine-Driven Auxiliary

Feed-water Pumps Extended Storage of Sealed Sources Improper Integration

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

Oil Reliability

of ATWS Mitigation

Systems and Other NRC-Required

Equip-ment not Controlled

by Plant Technical

Specifica- tion Unrecognized

Loss of Control Room Annunciators

Potential

Problem with Westinghouse

Rod Control System and Inadvertent

Withdrawal

of A Single Rod Control Cluster Assembly Degradation

of Shutdown Cooling System Performance

Operational

Challenges

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

authorized

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

License CP = Construction

Permit


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