ML20235V448
| ML20235V448 | |
| Person / Time | |
|---|---|
| Issue date: | 02/17/1989 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Quayle J, Jason Wright HOUSE OF REP., SPEAKER OF THE HOUSE, SENATE, PRESIDENT OF THE SENATE |
| Shared Package | |
| ML20235A877 | List: |
| References | |
| ACRS-R-1341, NUDOCS 8903100193 | |
| Download: ML20235V448 (6) | |
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'o,, UNITED STATES
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{o n, ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 g
February 17, 1989 The Honorable J. Danforth Quayle President of the United States Senate Washington, D.C. 20510
Dear Mr. President:
In accordance with the requirements of Section 29 of the Atomic Energy Act of 1954, as amended by Section 5 of Public Law 95-209, the Advisory Committee on Reactor Safeguards has reported each year to the Congress on the Safety Research Program of the Nuclear Regulatory Commission.
In our December 18, 1986 letter to the Congress, we proposed to provide more focused reports on specific research issues rather than one all-inclusive annual report. The Commission agreed with our suggestion, and NRC Chairman Zech submitted a legislative proposal in the form of -a draft bill to the 100th Congress on December 2, 1987 to amend Section 29 of the Atomic Energy Act of 1954 to accomplish this. Since the 100th Congress did not act on this matter, he has submitted a similar, but somewhat modified, legislative proposal on February 2, 1989 to the 101st Congress for consideration.
In the past year we have reviewed the NRC Safety Research Program and other closely related matters in the following areas:
- Containment Performance
- Containment Structural Integrity
- Equipment Qualification-Risk Scoping Study
- Embrittlement of Reactor Pressure Vessel Supports
- Fire Risk Scoping Study
- Human Factors Research Program Plan
- Incividual Plant Examination Program
- Inservice Inspection of Boiling Water Reactor Pressure Vessels 8903100193 890217 Iof s
. j PDR ACRS R-1341 PDC l. _ _ _ _ _ _ _
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The Honorable J. Danforth Quayle February 17, 1989
- Integration Plan for Closure of Severe Accident Issues
- Piping Integrity
- Safety Goal Policy Implementation Plan
- Severe Accident Management
- Thermal-Hydraulic Phenomena We have provided reports to the Commission and the NRC staff on several of the matters mentioned above and copies of these reports are attached.
We ' expect to continue to review various elements of the NRC Safety Research Program and provide reports to the Commission as warranted.
Sincerely, Forrest J. Remick Chairman Attachments:
- 1. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on Embrittlement of Structural Steel, March 15, 1988.
- 2. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on the Need for Greater Coherence Among New Regulatory Policies, March 15, 1988.
- 3. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on the Program to Implement the Safety Goal Policy, April 12, 1988.
- 4. Letter from William Kerr, ACRS Chairman, to Victor Stello, Execu-tive Director for Operations, U.S. NRC,
Subject:
Fire Risk Scoping Study, May 10, 1988.
- 5. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Proposed Generic Letter on Individual Plant Examinations and the Proposed Integrated Safety Assessment Program II, May 10, 1988.
The Honorable J. Danforth Quayle February 17, 1989
- 6. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC-Chairman,
Subject:
Inservice Inspection of Boiling Water. Reactor Pressure Vessels, June 7, 1988.
- 7. Letter from David A. Ward, Acting ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
NRC Research Related to Heat Transfer and Fluid Transport in Nuclear Power Plants, June 7, 1988.
- 8. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Report on the Integration Plan for . Closure of Severe Accident Issues (SECY-88-147), July 20, 1988.
- 9. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Report on NUREG-1150, " Reactor Risk Reference Document," August 16, 1988.
- 10. Letter from William Kerr, ACRS Chairman, to Lando'W. Zech, U.S. NRC Chairman,
Subject:
Equipment Qualification-Risk Scoping Study, December 20, 1988.
- 11. Letter from Forrest J. Remick, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Mark I Containment- Performance Im-provement Program, January 19, 1989.
- 12. Letter from Forrest J. Remick, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Code Scaling, Applicability, and Uncertainty (CSAU) Methodology for Determination of Uncertainty Associated With the Use of Rea li st '.c ECCS Evaluation Models, January 19, 1989.
- 13. Letter from Forrest J. Remick, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Further ACRS Comments on Implemen-tation of the Safety Goal Policy, February 16, 1989.
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- 'o,, UNITED STATES NUCLEAR REGULATORY COMMISSION
["
,, g y ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o g WASHINGTON, D. C. 20555 February 17, 1989 The Honorable Jim Wright Speaker of the United States House of Representatives L'ashington, D.C. 20515
Dear Mr. Speaker:
In accordance with the requirements of Section 29 of the Atomic Energy Act of 1954, as amended by Section 5 of Public Law 95-209, the Advisory Committee on Reactor Safeguards has reported each year to the Congress on the Safety Research Program of the Nuclear Regulatory Commission.
In our December 18, 1986 letter to the Congress, we proposed to provide more focused reports on specific research issues rather than one all-inclusive annual report. The Commission agreed with our suggestion, and NRC Chairman Zech submitted a legislative proposal in the form of a draft bill to the 100th Congress on December 2, 1987 to amend Section 29 of the Atomic Energy Act of 1954 to accomplish this. Since the 100th Congress did not act on this matter, he has submitted a similar, but somewhat modified, legislative proposal on February 2, 1989 to the 101st Congress for consideration.
In the past year we have reviewed the NRC Safety Research Program and other closely related matters in the following areas:
- Containment Performance
- Containment Structural Integrity
- Equipment Qualification-Risk Scoping Study
- Embrittlement of Reactor Pressure Vessel Supports
- Fire Risk Scoping Study
- Human Factors Research Program Plan
- Individual Plant Examination Program
- Inservice Inspection of Boiling Water Reactor Pressure Vessels i
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! The Honorable' Jim Wright February 17, 1989 1
- Integration Plan for Closure of Severe Accident Issues
- Piping Integrity
- Safety Goal Policy Implementation Plan
- Severe Accident Management
- Thermal-Hydraulic Phenomena We have provided reports to the Commission and the NRC staff on several of the matters mentioned above and copies of these reports are attached.
We expect to continue to review various elements of the NRC Safety !
Research Progran and provide reports to the Commission as warranted.
Sincerely, Forrest J. Remick Chairman Attachments:
- 1. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on Embrittlement of Structural Steel, March 15, 1988. :
- 2. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on the Need for Greater Coherence Among New Regulatory Policies, March 15, 1988.
- 3. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
ACRS Comments on the Program to Implement the l Safety Goal Policy, April 12, 1988.
- 4. Letter from William Kerr, ACRS Chairman, to Victor Stello, Execu-tive Director for Operations, U.S. NRC,
Subject:
Fire Risk Scoping i Study, May 10, 1988.
-5. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC 4 Chairman,
Subject:
Proposed Generic Letter on Individual Plant !
Examinations and the Proposed Integrated Safety Assessment Program II, May 10, 1988.
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l l l The Honorable Jim Wright February 17, 1989
- 6. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Inservice Inspection of Boiling Water Reactor Pressure Vessels, June 7, 1988.
- 7. Letter from David A. Ward, Acting ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
NRC Research Related to Heat Transfer and Fluid Transport in Nuclear Power Plants, June 7, 1988.
- 8. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Report on the Integration Plan for Closure of Severe Accident Issues (SECY-88-147), July 20, 1988.
- 9. Letter from William Kerr, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Report on NUREG-1150, " Reactor Risk Reference Document," August 16, 1988.
- 10. Letter from William Kerr, ACRS Cha1rman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Equipment Qualification-Risk Scopin9 Study, December 20, 1988.
- 11. Letter from Forrest J. Remick, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Mark I Containment Performance Im-provement Program, January 19, 1989.
- 12. Letter from Forrest J. Remick, ACRS Chairman, to Lando W. Zech, U.S. NRC Chairman,
Subject:
Code Scaling, Applicability, and Uncertainty (CSAU) Methodology for Determination of Uncertainty Associated With the Use of Realistic ECCS Evaluation Models, January 19, 1989.
- 13. Letter from Forrest J. Remick, ACRS Chairman, to Lando 'W. Zech, U.S. NRC Chairman,
Subject:
Further ACRS Comments on Implemen-tation of the Safety Goal Policy, February 16, 1989.
- 'po anc 'o UNITED STATES l' . , . p, NUCLEAR REGULATORY COMMISSION
{ j ADVISORY COMMITTEE ON REACTOR SAFEGUARDS wAssmatoN, p. c.20sss o,
~*,,,,*~f March 15, 1988 The Honorable Lardo W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Zech:
SUBJECT:
ACRS COMMENTS ON EMBRITTLEMENT OF STRUCTURAL STEEL There has been a recent exchange of letters between the ACRS and the NRC cencerning the possibility of threats to the safety of nuclear power plants due to the trore rapid than expected embrittlement of pressure vessel supports from radiation at low temperatures. During the 335th meeting of the ACRS, March 10-12, 1988, we heard presentations from the NRC Staff on its further evaluation of this matter. Our Subcommittee on Metal Components met on February 18, 1988 to discuss this matter.
We believe that the program the NRC Staff is undertaking to resolve this matter is appropriate. There are clearly important uncertainties remaining but the effort being implemented should generate the informa-tion needed in a timely manner. We would like to be kept informed on the progress and resolution of this matter.
Sincerely.
William Kerr Chaiman
References:
- 1. Letter dated July 15, 1987 from William Kerr, ACRS Chairman, to Victor Stello, Jr. Executive Director for Operations, U.S. NRC, l
Subject:
ACRS Coments on the Embrittlement of Structural Steel
- 2. Memorandum dated October 7, 1987 from Victor Stello, Jr., Executive i
Director for Operations, U.S. NRC, to William Kerr, ACRS Chaiman, Regarding the Embrittlement of Structural Steel
- 3. Letter dated December 8,1987 from William Kerr, ACRS Chaiman, to Victor Stello, Jr., Executive Director for Operations U.S. NRC,
Subject:
ACP.S Coments on Memorandum from Victor Stello, Jr., EDO, dated October 7,1987 Regarding the Embrittlement of Structural Steel M EbE Attachment 1
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!' .4 'g NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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W ASHINGTON, D. C. 20666 o,
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March 15, 1988 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Zech:
SUBJECT:
ACRS COMMENTS ON THE NEED FOR GREATER COHERENCE AMONG NEW REGULATORY POLICIES During the 335th meeting of the Advisory Committee on Reactor Safeguards (ACRS), March 10-12, 1988, we discussed the problem which we see as an increasing lack of coherence and integration among several separate areas of policy making within the NRC. We understand that the NRC Staff is atterpting to develop an integrated ; approach to implementing the Comrission's Severe Accident Policy. In the usual course of events, we would expect to review the Staff's proposals at a later date. However, we believe it might be helpful to forward a few comments to you at this time.
The Severe Accident Policy is only one of a number of new Consnission policies and programs concerning nuclear power plants that have been advanced over the past two or three years. Others relate to the safety goal, standardized plant designs, ISAP, and advanced reactors. In addition, the resolution of USIs and GIs has led, or might lead, to important new requirements and guidance for ifcensees in several areas.
Although the NRC Staff, the ACRS, and the Commission have provided some overall guidance toward integration of these policies and new require-i
' ments, we believe this has been insufficient. As a result, licensees can be confused or burdened with contradictory new requirements from different parts of the NRC Staff.
For example, a part of the resolution of USI A-45, " Shutdown Decay Heat Removal Requirements," proposed some months ago, incorporated the use of safety objectives similar to, but not the same as, objectives being l
' developed in implementation of the Safety Goal Policy.
Attachment 2 l
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- The Honorable Lando W. Zech, Jr. March 15, 1988 We offer two suggestions for your consideration:
(1) The attempt to integrate evolving policies and issues should not be limited to those embodied in the Severe Accident Policy, but should incorporate the entire range necently addressed in policy state-ments or currently before the Commission.
(2) The Safety Goal Policy should not be viewed as just one of the several policies and issues on today's table. Instead, it should be seen as an umbrella policy which should be the principal tool for integrating and providing coherence to the entire set.
We expect to review the integratioti program being developed by the NRC Staff when it is available.
Sincerely, William Kerr Chainnan
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