ML20028H316
| ML20028H316 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1990 |
| From: | Hoyle J Advisory Committee on Reactor Safeguards |
| To: | LIBRARY OF CONGRESS |
| Shared Package | |
| ML20028H317 | List: |
| References | |
| ACRS-GENERAL, NUDOCS 9012110135 | |
| Download: ML20028H316 (3) | |
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UNITED $T Af f s
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November 6, 1990
'..... <j OF f ICE OF THE St Clit i A$tY Eederal Advisory Committee Desk redoral Documents Section Exchange and Gift Division Library of Congrecs Washington, D.C.
20540
Dear Sir:
Enclosed are eight copics of the reports and background papers of the Advisory Committoo on Reactor Safeguards for placement in the Advisory Committoo depository.
Sincerely,
,\\ ](%f3 Y Nm
/Y John C.
Hoyle Advisory Committoo Management Officer
Enclosure:
ACRS Committee and Consultant Reports --
182 - October 1990 bht 9012110135 901106 i
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ACRS COMMITTEE AND CONSULTANT REPORTS - 182 Submitted in Accordance with Sections 10 and 13 of the Federal Advisory Commit.ee Act i
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SUMMARY
LETTER 10/31/90 1
II)
ACRS REPORTS TO CU'"isMAN, NRC 1.
Lewis 1tr to Carr, re Legal Services 10/12/90 for the ACRS 4
III)
ACRS REPORTS TO EXECUTIVE DIRECTOR FOR OPERATIONS, NRC 1.
Michelson ltr to Taylor, NRC Computer 10/11/90 Codes and Their Documentation 2.
Michelson lir to Taylor, Draft Implementation 10/11/90 Documents for the Proposed License Renewal Rule I
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October 31, 1990 The flororable Kenneth M.
Carr Chairman U.S. Nuclesr Regulatory Commission Washincton, D.C.
20555 Dear Chalirman Carr
SUBJECT:
SUMMARY
REPORT - THREE HUNDRLD SIXTY SIXTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, OCTOBER 4-6, 1990 During its 366th meeting, October 4-6, 3 990, the Advisory Committee on Reactor Safeguards discussed several matters and completed the report and letters noted below.
In
- addition, the Committee authorized Mr. Fraloy to transmit the menoranda identified below.
Efl2QRTJ Q THE CJQMtR EG1DH Ecport t9__ChalInnu._ Corr ReLainst to Legal servises for tlm m
ACER. dated Qstntler..12. 1990.
LETTER $
e Draf;t IJaplementation Documents for the Proppsed License Per+ val Rule (Letter to James M.
- Taylor, EDO, acted October 11, 1990.)
ERC_Copenntsr,f.qdes anst Tneir Documentation (Letter to James M.
Taylor, EDO, dated October 11, 1990.)
lifllQEARRA hypoirttnent of ACRS Members (Memorandum for Chairman Carr from l
R.
F.
Fraley, dated October 12, 1990.)
Periodic ACRS_ijectina With the Cofmissioners (Memorandum for e
Samuel J.
- Chilk, Secretary of the Commission from R.
F.
Fraley, dated October 12, 1990.)
Amendment to 10 CFR Part 34: _hSNT Certification of Industrial l
e Basticaraphers (Memorandum for Donald A. Cool, Chief, Radiation Protection and Health Effects Branch, RES, from R.
F. Fraley, dated October 12, 1990.)
The Honorable Kenneth M.
Carr 2
October 31, 1990 Mr. Fraley has informed Mr. Cool that the Committee members have decided not to review this proposed Amendment to 10 CFR Part 34.
Consideration of Turkey Point Standardized Technical Specifications (Momorandum for Fotor B. Blocia, Administrative Judge, ASLB, from R.
F.
Fralcy, dated October 15, 1990.)
The Committeo decided not to take further action regarding Mr. Bloch's request, contained in his September 25, 1990 memorandum, that the ACRS consider the safety significance of several matters of concern to the ASLB regarding the use of standardized technical specifications for the Turkey Point Plant, Units 3 and 4.
HIGHLIGHTS OF CERTAIN MATTERS CONSIDERED BY THE COMMITTEI e
License Renewal Staudard Review Plan and Associated Draft Reaulatory Guidq The Committee heard presentations by and held discussions with members of RES and NRR with regard to the following documents that are intended to provide guidance for implementing the provisions of the proposed license renewal rule, 10 CFR part 54:
Draf:
.egulatory Guido, Task DG-1009, " Standard Format and i ontent of Technical Information for Applications to Renow Nuclear Power Plant Operating Licenses."
Draft NUREG-1299,
" Standard Review Plan License Renewal."
The Committee provided several comments and recommendations to the EDO on this matter.
The Committee agrood that the proposed Regulatory Guido and NUREG-1299 should be issued for public comment and stated that it plans to continue its review of this matter after the public comments on the proposed 10-CFR Part 54, the Regulatory Guide, and the proposed NUREG-1299 have been *ccoived and assimilated.
Documentation of NRC Computer Codes The Committee discussed the adequacy of documentation of NRC computer codes, especially of those in the thermal hydraulic and severo accident areas.
The Committee provided a letter to the EDO on this matter, including several comments and recommendations.
The Committee stated that the RES program managers should ensure that adequate documentation is provided in a timely manner, particularly for models and correlations
5 i
The Honorable Kenneth M. Carr 3
October 31,-1990 and_ developmental _ assessment.
The Committee suggested that the NRC-make sufficient funding!and resources available to ensure that the documentation associated with the development of the agency's codes is adequate.
e
=ADDointment of ACRS Members The' Committee members continued their review of the qualifications of candidates for appointment to the ACRS.
Based on the review of'the. qualifications of 46 candidates, i
the members selected a ' panel - of three - candidates for the position on the ACRS that will open on February 23, 1991.
As inttructed by the Committee, Mr. Fraley transmitted the na.nes of these three candidates to the Commission on
. October-12, _1990, requesting that the Commission make its selection by the end of December 1990.
The Committee plans to recommend to the Commission an additional panel of candidates at a later date -for the position that will open on May 9, 1991.
&QRS Meetinct with the Commissioners e
The : Committe'e is scheduled to meet with the Commissioners
[
between 2:00 3:30 p.m.
on Thursday, November 8, 1990, to i
discuss various items of. mutual interest.
After considering the_ topics-proposed by the Committee, the Commissioners:have chosen the following items for discussion during this meeting:'.
Essentially Complete Design Level of Design Detail' Under 10 CFR Part 52.
S urce Term update and Decoupling Siting from Plant Design.
Proposed Resolution of Generic. Issue B-56, Diesel
. Generator Reliability.
Status of ACRS Formulation of Containment Design Criteria' for Future Plante.
Reeval'uation-of the Systematic Assessment of Licensee Performance (SALP) Program, i
e Advanced Reactors-Members _of the NRC staff briefed the Committee regarding their plans:for review of Advanced Reactor = designs'(CANDU-3, PIUS,.
MHTGR, and'LMR).
The staff stated that the Commission, in its FY 1992-1993. budget request to the
- OMB, has requested
ne Honorable Kenneth M. carr 4
October 31, 1990 resources to support the review of the CANDU-3 and PIUS designs.
As directed by the Commission, the staff plans to assign 2 FTE each to the CANDU-3 and PIUS design reviews during FY 1991.
This was an information briefing the Committee took no action.
EnrLory_Allg_q-Based OA Representatives of the NRC staff briefed the Committee regarding the proposed revision to Chapter 17,
" Quality Assurance,H of the Standard Review Plan (SRP).
This revision incorporates, as appropriate, the results of the QA study performed in 1984 by the NRC staff and its consultants as mandated by the Congress.
The staff has added Soution 17.3 to Chapter 17 of the SRP to describe a performance-based QA program so as to incorporate one of the major findings of the above mentioned study that QA should focus more on the performance of each individu.11, including management personnel.
This was an information briefing - the Committee took no action.
International Activities Members of the NRC delegation of the Joint Coordinating Committee for Civilian Reactor Safety, who met in the U.S.S.R.
during the period of June 25 through July 9, 1990, briefed the Committee regarding the U.S.S.R.
practices in the following areas:
Erosion and corrosion of piping and components.
Embrittlement and Annealing.
Severe Accidents.
This was an information briefing - the Committee took no action.
NUREG-1150, Severe Accident R i s :.g An Assessment for Five U.S. Nuc_ Lear Power Plants The Committee considered a draft report to the Commission on NUREG-1150 and decided to continue the discussion of this matter during the November 8-10, 1990 ACRS meeting.
The lionorable Kenneth M.
Carr 5
October 31, 1990 e
Annual ACRS Report to the Concress The Committee discussed the scope, format, and content of the forthcoming ACRS report to the Congress on the NRC Safety Research Program and budget and decided to use a format similar to that used for last year's report, llowever, the transmittal letter of the report may be
- expanded, as necessary, to include comments and recommendations on the ongoing and proposed NRC Safety Research Program and budget that the Committee considers important.
The Committee agreed that Dr. Catton, the Safety Research Program Subcommittee Chairman, should consider an integrated report on the NRC Safety Research Program and budget for submittal to the Commission during next year.
MDLGQMMITTEE IJEETINGS Fince the last summary report of ACRS activities, the following Subcommittee meetings have been held:
My.anced Pressurized Water Reactors. September 21, 1990 e
The Subcommittee met with representatives of Combustion Engineering, Inc., and discussed the feedback from operational experience at CE plants, in particular at the Palo Verde Nuclear Plant, for the CE System 80+ design.
Plant License Renewal. October 2, 1990 The Subcommittee reviewed the draf t Regulatory Guide, Task DG-1009, " Standard Format and Content of Technical Information for Applications to Renew Nuclear Po.er Plant Operating Licenses," and draft NUREG-1299, "Stardard Review Plan License Renewal."
e Joint Severe Accidents, Extreme External Phenomena, and Erobabilistic Risk Assessment, October 3.
1990 The Subcommittees continued their discussion of NUREG-1150,
" Severe Accident Risks:
An Assessment for Five U.S.
Nuclear Power Plants," in the areas of seismic and fire analye.es.
Imoroved Licht Water Reactors, October 31, 1990 The Subcommittee reviewed the latest NRC staff proposal regarding the level of design detail under 10 CFR Part 52.
s 9
The Honorable :.anneth M.
Carr 6
October 31, 1990 Advanced Boilina Water Reactors October 31 _1SSA e
The Subcommittee reviewed the physical separation and general plant layout for the GE Advanced Boiling Water Reactor design.
FUTURE ACTIVITIES The Committee agreed to tne following tentative schedule for the 367th, November 8-10, 1990, ACRS meeting:
Severe Accident Risks:
An Assessment for Five U.
S.
Nuclear Egwer Plants (NUREG-1150)
(Onen)
Continue preparation of ACRS report to the NRC regarding the merits and use of this document.
Reactor Operatina Exparience (Onen/ Closed)
Briefing and discussion regarding lessons learned from nuclear power plant operating experience including problems with the operability of safety systems from noncondensible gasses, loss of off-site power and main steam isolation valve closure events at the Brunswick nuclear station, and a feedwater transient and subsequent failure of the RCIC system which occurred at the Pilgrim nuclear station.
(NOTE:
This item has been deferred.)
e Level of Desian Detail (Onen)
Briefing and discussion on level of design detail needed for new standard plant reviews, e
Meetina with NRC Commissioners (Open)
Discuss safety-related issues on matters that the Committee has been or is in the process of reviewing, e
30 CFR Part 55. Fitness for Duty Recuirements for Licensed Operators (Onen)
Review and report on the proposed final version of the Fitness for Duty Rule.
NRC Reculatory Imnact Survey (Onen) - Briefing and discussion of proposed NRC actions resulting from the regulatory impact survey.
Prepare ACRS report to NRC, as appropriate.
Biolonical Effects of Ionizina Radiation (Onen)
Briefing regarding Report V of the National Research Council Committee on the Biological Effects of Ionizing Radiation.
ACRS Subcommittee Activities (Onen) - Reports and discussion of ACRS subcommittee activities regarding assigned safety-related matters such as the proposed containment design critoria for future plants, interfacing systems LOCA, and reconstitution of design basis documentation.
Radioactive Waste Disposal (Open) - Briefing and discussion l
regarding the report on Rethinking High-Level Radioactive Waste Disposal prepared by the National Research Council Board on Radioactive Waste Management.
(NOTE:
This item has been deferred.)
Combustion Enaineerina System 80+ (Onen/ Closed) - Review and l
e report on proposed Licensing Review Basis (LRB) for CE System l
80+ design.
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The lionorable Kenneth M.
Carr 7
October 31, 1990 F_t;1tndardizpfl Nuclear
- Plant, Westinghouse SP/90 Desicin e
Review and comment on the proposed PDA for (Open/ Closed) this standardized nuclear plant, Performance of Solenoid Valves at Nuclear Power Plants (Ooon) o Briefing on the status of AEOD's work on the evaluation of solenoid valve problems at nuclear power plants.
(NOTE:
This item has been deferred.)
Anticipated ACRS Activities (Open1 - Discuss anticipated ACRS subcommittee activitics and items proposed for consideration by the full Committee.
Proposed dates for CY 1991 ACRS full Committee moctings will also be discussed.
Incomplete items from previous Committee meetings will be discussed as timo and availability of information permit.
Sincerely, 4ff J/G u ~
Carlyle Micholson Chairman
.~
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, je UNITED STATES g
NUCLEAR REGULATORY COMMISSION g
g a e ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20S$5 October 12, 1990 The Honorable Kenneth M.
Carr Chairman U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Carr:
We have your memorandum of August 1,
1990, dealing with legal services for the Advisory Committee on Reactor Safeguards.
We wish to comment on the implication in your memorandum that the ACRS role is to provide " scientific and technical" advice to the Commission and to spell out a bit more carefully the basis for the position taken by the ACRS in a letter to you dated July 17, 1990.
The basic documents that specify the ACRS duties are Section 29 of the Atomic Energy Act, as amended, and the provisions contained in 10 CFR 1.13.
You imply in your memorandum that these documents define the ACRS role as one of giving " scientific and technical advice" to the Commission, but the fact is that no an6 language is contained in either.
To the contrary, both docure.tcs refer to advice on a variety of safety-related matters.
atil now Commission and no Chairman have defined limits to this assignmet Although the July 17 letter called this matter to your attention, it now appears that it would be helpful to explain more carefully just why it is important to reactor safety that we have the freedom to explore (including the use of appropriate consultants) all those aspects of a safety-related question that we deem important.
The point made in the July 17 letter is that independence only on narrowly technical matters is unduly limiting.
The nub of the issue is that reactor safety is a complex mix of technical, procedural, human, and legal matters.
For any given safety question one or another of these factors may dominate, and to limit the areas of investigation in advance is to seriously impair the ability of the Committee to function in its statutory role.
Perhaps some examples will help, e
In 1986 the '.nterpretation of the backfit rule was a pressing
- issue, involving both the extent to which a cost-benefit analysis could be required as justification for a backfit, and the definitiori of adequate protection.
The Commission had already received a report from OGC on these matters, but the Committee felt that, in its role as an independent advisor to the Commission, it required a
separate analysis.
The Committee then engaged an outside law firm to study the issues l
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mees en
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-The lionorable Kenneth M.
Carr 2
October 12, 1990 on its behalf, and that study materially contributed to its understanding.
In _this case, the legal issues were in-separable from the technical ones.
Though we have_yet to report to you on this, we have recently had a series of briefings on the criteria the staff has used to order a plant shut down and to permit it to restart.
This discussion has raised, in some of our minds,: serious questions about accountability for each of these decisions.
Both for shutdown-and for restart, the staff criteria were highly _
personal and subjective in areas (like " management culture")
that lack explicit standards.
Whether it is in the interests o f_ nuclear safety 'for the licensee to be forced to simply placate-the staff under these conditions is at best ques-tionable.
Certainly the staff has limited expertise in such areas.
These are two (of many that could have been furnished) examples of important safety-related matters, which are not narrowly " sci-entific and technical."
The Committee is required by both law and conscience to advise you about all aspects of safety-related matters, without topical constraints.
This will occasionally require that we seek outside consultation on a variety of subjects when a second opinion seems appropriate,, even though the advice available from your staff may well be competent.
(Such outside-
= consultation may well involve legal matters.)
After all, it is the staff that advises you, nnd our independence is illusory if.we are confined to that same staff for our own inputs.
Once more we ask you to take those matters seriously -- they go to the 1 heart of the _ relationship between the Commission and the Committee.__'We do not raise them lightly, and urge you to recon-sider.the' position taken in your memorandum of August 1, 1990.
-Additional comments by ACRS Memoers Carlyle Michelson and Charles J. Wylie',.and by Chester P.
Siess are presented below.
Sincerely,
/
~
Harold W.. Lewis
-Acting Chairman Mditional Comments by ACRS Members Carlyle Micholson and Charles J. Wylie It is our position that Chairman Carr's memorandum of August 1, 1 9 9_0, constitutes'an adequate reply to the ACRS letter of July 17, 1990.
We believe that the ACRS is not constrained in pursuit of
-=
The Honorable Kenneth M.
Carr 3
October 12, 1990 its responsibilities as defined by the Atomic Energy Act and by Federal regulations.
If it should require legal assistance concerning a specific matter, the Office of the General Counsel is ready and willing to support such a need.
If the Committee should feel that independent legal assistance is essential, the Commission has ensured that such a need can be brought to its attention for resolution.
To our knowledge, the Committee has never been encumbered in its ef forts to find and retain outside scientific or technical assistance.
It is our view that this matter has already achieved a proper closure and should be dropped.
Additional Comments by ACRS Member Chester P.
Siess I cannot agree with my colleagues that my ability to provide advice to the Commission on matters of reactor safety is seriously impaired by anything you wrote in your memorandum of August 1, 1990.
,