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

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
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)

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:

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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