ML20205S805
| ML20205S805 | |
| Person / Time | |
|---|---|
| Issue date: | 04/22/1999 |
| From: | Powers D Advisory Committee on Reactor Safeguards |
| To: | Travers W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-R-1821, NUDOCS 9904270027 | |
| Download: ML20205S805 (2) | |
Text
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ACRSR-1821
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UNITED STATES PDR d'
NUCLEAR REGULATORY COMMISSION n
I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHIN;. TON. D. C. 20665 Apa' 22,1999 Dr. Wdliam D. Travers Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Dear Dr. Travers:
SUBJECT:
STATUS OF RESOLUTION OF STEAM GENERATOR TUBE INTEGRITY ISSUES During the 461s' meeting of the Advisory Committee on Reactor Safeguards, April 7-10,1999, we reviewed the staff and industry activities associated with steam generator tube integrity issues. During our review, we had the benefit of discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEl), and of the documents referenced.
Conclusions and Recommendations 1.
The NRC staff and the industry have several unresolved technical and regulatory differences associated with ensuring steam generator tube integrity. The staff and industry should continue to work toward the resolution of these differences.
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2.
The staff is in the process of resolving the differing professional opinion (DPO) issues associated with steam generator tube integrity. We plan to review the staff's resolution of the DPO issues after reconciliation of public comments.
9(
Discussion N
We last reviewed the issues associated with steam generator tube integrity during our 444*
meeting on September 3-5,1997, and provided a report to the Commission dated September l
15,1997. At that time, we agreed with the staff's decision not to proceed with rulemaking and l
recommended that a proposed generic letter and draft Regulatory Guide (DG) 1074, " Steam Generator Tube Integrity," be issued for public comment. We believed that the specifications contained in the proposed generic letter and DG-1074 would improve the integrity of steam generator tubes by having licensees do condition monitoring, operational assessment, and qualification of nondestructive examinations, in December 1997, the industry committed to implement, on a voluntary basis, NEl 97-06,
" Steam Generator Program Guidelines." The programmatic approach of NEl 97-06 is i
9904270027 990422
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conceptually similar to that specified in DG-1074. Consistent with Direction Setting issue 13, "The Roltof industry," the sta# held discussions'with the industry concoming resolution of the differences between NEl 97-06 and DG-1074, and the establishment of an appropriate regulatory framework for implementing NEl guidelines. Anticipating resolution of these differences through additional interactions with the industry, the staff postponed the issuance of
. the proposed generic letter and withdrew the associated advance notice of proposed rulemaking The staff and industry now plan to resolve the remaining technical differences, such as the definition of the differential pressure on a steam generator tube, the choice of an accident induced leakage limit, the definitions of tube burst and tube rupture, and the risk issues associated with probabilistic structural criteria. Following the resolution of these differences, NEl plans to propose to the staff performance-based technical specifications for ensuring steam generator tube integrity. The staff plans to review the NEI proposal and prepare a safety evaluation report, which would allow licensees to request license amendments to modify their
- technical specifications. We plan to review the results of these efforts.
ACRS member Dr. William J. Shack did not participate in the Committee's deliberations on this matter.
Sincerely,
\\
d W%D Dana A. Powers Chairman
References:
1.
SECY-98-248, Memorandum dated October 28,1998, from Willliam D. Travers, Executive Director for Operations, NRC, for the Commissioners,
Subject:
Proposed Generic Letter 98-XX, ' Steam Generator Tube Integrity."
2.
Letter dated December 16,1997, from Ralph E. Beedle, Nuclear Energy Institute, to L.
Joseph Callan, Executive Director for Operations, NRC,
Subject:
NEl 97-06, " Steam Generator Program Guidelines."
3.
ACRS letter dated October 10,1997, from R. L. Seale, Chairman, ACRS, to L. Joseph Callan, Executive Director for Operations, NRC,
Subject:
Resolution of the Differing Professional Opinion Related to Steam Generator Tube integrity.
4.
ACRS report dated September 15,1997, from R. L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC,
Subject:
Proposed Generic Letter and Draft Regulatory Guide DG-1074 Concoming Steam Generator Tube Integrity.
5.
ACRS report dated June 20,1997, from R. L. Seale, Chairman, ACRS, to Sh!riey Ann Jackson, Chairman, NRC,
Subject:
Proposed Regulatory Approach Associated With Steam Generator Integrity.
6.
ACRS letter dated November 20,1996, from T. S. Kress, Chairman, ACRS, to James M.
Taylor, Executive Director for Operations, NRC,
Subject:
Proposed Rule on Steam Generator integrity.
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