NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl

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Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl
ML20247B513
Person / Time
Issue date: 01/25/1989
From: Stello V
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Sharp P
HOUSE OF REP., ENERGY & COMMERCE
Shared Package
ML20245E981 List:
References
REF-GTECI-A-03, REF-GTECI-A-04, REF-GTECI-A-05, REF-GTECI-SG, RTR-NUREG-0844, RTR-NUREG-844, TASK-A-03, TASK-A-04, TASK-A-3, TASK-A-4, TASK-A-5, TASK-OR NUDOCS 8903290409
Download: ML20247B513 (2)


Text

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/ 'o UNITED STATES i

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$ WASHINGTON, D. C. 20555 h

%.,,,./ January 25, 1989 i

The Honurable Philip R. Sharp, Chairman Subcommittee on Energy and Power Committee on Energy and Commerce United States House of Reprt:entatives Washington, D.C. 20515

Dear Mr. Chairman:

Enclosed for the information of the Subcommittee en Energy and Power is a copy of NUREG-0844, "NRC Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity."

This issuesrep (ort documents the final resolution of the subject unresolved safet USIs).

Steam generator tube integrity was designated an unresolved safety issue in 1978 after it became apparent that steam generator tubes were subject to widespread degradation, frequent leaks, and occasional ruptures (i.e., gross failures). Task Action Plans A-3, A-4, and A-5 were established to evaluate the safety significance of these problems for Westinghouse, Combustion ,

Engineering, and Babcock & Wilcox steam generators, respectively. These studies were later combined into one effort because many problems being experi-enced by the different pressurized-water reactor (PWR) vendors were similar.

The enclosed report provides a generic risk assessment that indicates that risk from steam generator tube rupture (SGTR) events is not a significant contributor to the total risk at a given site, nor to the total risk to which the general public is routinely exposed. This finding is considered indicative of the effer.tiveness of licensee programs and regulatory requirements for ensuring steam generator tube integrity in accordance with 10 CFR 50, Appendi-

ces A and 8.

NUREG-0844 also identifies a number of staff-recommended actions that can further improve the effectiveness of licensee programs in ensuring the integ-rity of steam generator tubes and in mit.igating the consequences of an SGTR.

As part of the integrated program, the staff issued Generic Letter 85-02 encouraging licensees of PWRs to upgrade their programs, as necessary, to meet the intent of the staff-recommended actions; however, such actions do not constitute NRC requirements. In addition, this report describes a number of ongoing staff actions and studies involving steam generator issues that are being pursued to provide added assurance that risk from SGTR events will continue to be small.

The staff will continue to monitor steam generator operating experiences as an indicator of the effectiveness of licensee programs for ensuring steam genera-tor tube integrity. As has been true in the past, the staff may impose additional 8903290409 890125 COMMS NRCC PDR f

CORRESPONDENCE PDv,

( -- - _ . _ _ _ _ _ _ _ _ _ _ ___

/ .

The Honorable Philip R. Sharp i requirements (pursuant to applicable regulations) to continue to ensure that licensees are implementing adequately effective programs where and if such action is determined to be necessary on the basis of operating experience or as a result of ongoing staff actions and studies.

Sincerely, 1 y!f VictorStello[Jr.

Executive Director for Operations

Enclosure:

NUREG-0844 cc w/ enclosure:

Rep. Carlos Moorhead l

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