ML20129G776
"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.
| ML20129G776 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Catawba  |
| Issue date: | 08/09/1996 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| TASK-*****, TASK-RE ACRS-3021, NUDOCS 9610070288 | |
| Download: ML20129G776 (38) | |
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Issue Date:
8/9/96 Uw d
M g gyg TABLE OF CONTENTS MINUTES OF THE 432ND ACRS MEETING JUNE 12-14, 1996 Pace I. Chairman's Report (Open) 1 II. Draft Regulatory Guide, DG-1047, " Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses" (Open) 1 III. IPE Insights Report (Open) 4 IV. Loss of Offsite Power at Catawba, Unit 2 (Open) 6 V. Issues Associated with Steam Generators (Open) 8 VI. Browns Ferry Nuclear Plant, Unit 3 (Open).....
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VII. Health Effects of Low Levels of Ionizing i
Radiation (Open) 11 VIII. Executive Session (Open) 14 i
A.
Reports, Letters, and Memorar.da Severe Accident Research (Report to Shirley Ann
- Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated June 28, 1996.)
Draft Reculatory Guide DG-1047.
" Standard Format and Content for Acolications to Renew Nuclear Power Plant Operatino Licenses" (Letter to James M.
- Taylor, Executive Director for Operations, from T.S.
Kress, Chairman, ACRS, dated June 18, 1996)
B.
Reconciliation of ACRS Comments ar.d Recommen-dations C.
Report on the Meeting of the Planning and Proce-dures Subcommittee Held on June 11, 1996 (Open)
D.
Future Meeting Agenda
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[ pc PEit. E Ecu cracl y n 4,.4 3
APPENDICE3 I.
Federal Register Notice II. Meeting Schedule and outline III. Attendees IV. Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee 4
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1 MINUTES OF THE 432ND MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS JUNE 12-14, 1996 ROCKVILLE, MARYLAND The 432nd meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on June 12-14, 1996.
The purpose of this meeting was to discuss and take appropriate action on the items i
listed in the attached agenda.
The meeting was open to public attendance.
There was one request for time to make an oral state-ment from a member of the public regarding the meeting.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W.,
Washington, D.C.
[ Copies of the transcript j
are available for purchase from Neal R. Gross and Co.,
Inc., 1323 Rhode Island Avenue, N.W., Washington, D.C. 20005.]
ATTENDEES ACRS Members :
Dr. Thomas S. Kress (Chairman), Dr. George Apostola-
- kis, Dr.
Ivan Catton, Dr.
Mario H.
Fontana.
Mr.
William J.
Lindblad, Dr. Don W.
Miller, Dr. Dana A.
Powers (did not attend Wednesday and Thursday), Dr. William J.
Shack, and Mr. Charles J.
Wylie.
(For a list of other attendees, see Appendix III.]
I.
CHAIRMAN'S REPORT (Open)
[ Note:
Dr. John T. Larkins was the Designated Federal Of ficial for this portion of the meeting.]
Dr. Thomas S. Kress, Committee Chairman, convened the meeting at 1:00 p.m. and reviewed the schedule for the meeting.
He annot" ed that Mr. John Barton, an ACRS nominee, was attending the meeting as an observer, and that Cindy Hsu was returning to the ACRS as a summer intern.
He also drew the Committee's attention to a speech by Chairman Jackson to the Nuclear Energy Assembly on May 30, 1996.
II.
Draft Reculatorv Guide. DG-1047. " Standard Format and Content for Aeolications to Renew Nuclear Power Plant Ooeratina Licenses" (Open)
(Note:
Dr.
M.
El-Zeftawy was the Designated Federal Official for this portion of the meeting.]
Introduction Dr. Fontana, Chairman of the Plant License Renewal Subcommittee, stated that the purpose of this session was for the Committee to hear a presentation by the NRC staf f regarding the Draf t Regulatory
- - -.~ - --.
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432nd ACRS Meeting 2
]
June 12-14, 1996 4
1 Guide, DG-1047, " Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses;" and to hear a presentation by representatives of the Nuclear Energy Institute
]
(NEI) regarding NEI 95-10, Revision 0.
l NRC Staff Presentation J
l I
)
Mr. Scott Newberry, NRR, noted that in December 1991, NRC published 10 CFR Part 54 to establish the procedures, criteria, and standards governing nuclear plant license renewal.
Since publishing the original rule, NRC and the industry had conducted various activi-i ties related to its implementation.
In September 1994, NRC i
j proposed an amendment to the rule.
The final amendment was published in May 1995.
It focuses on the effects of aging on long-lived passive structures and components and time-limited aging 1
analyses.
In addition, the amendment allows greater reliance,on i
the current licensing basis, the Maintenance Rule, and existing l
plant programs.
I Mr. Steve Hoffmann, NRR, stated that NEI had prepared a guideline j
document (NEI 95-10, Revision 0 - dated March 1996) that provides l
an industry guideline for implementing the License Renewal Rule.
i i
Applicants interested in license renewal are responsible for the i
preparation of a plant-specific license renewal application that i
d includes technical information such as an integrated plant assessment, current licensing basis changes during the NRC review i
of the application, a Final Safety Analysis Report (FSAR) supple-l ment, and a supplement to the plant's environmental report that complies with the requirements of Subpart A of 10 CFR Part 51.
l l
The NRC staff has prepared Draft Regulatory Guide, DG-1047, which provides a uniform format and content acceptable to NRC for 3
structuring and presenting the information to be submitted in an application for license renewal.
Conformance with this guide is
)
not required; however, its use facilitates both preparation of a license renewal application by a licensee, and a timely and uniform review by the staff.
A different format will be acceptable if it i
provides an adequate basis for approval.
4 The guidance provided in DG-1047 is expected to ensure that actions have been taken or will be taken regarding: 1) managing the effects of aging during the ' extended period of operation on the functional-ity of structures and components that have been identified to
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require review and 2) evaluating time-limited aging analyses that I
have been identified to require
- review, such that there is i
reasonable assurance that the activities authorized by the renewed 1
license will continue to be conducted in accordance with the l
current licensing basis.
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g 432nd ACRS Meeting 3
June 12-14, 1996 The Draft Guide (DG) endorses NEI 95-10, Rev.
0.
The staff's future activities include visiting sites to review an ir.dustry demonstration program that will help validate the NEI document, conduct a public workshop during the comment period for the DG, review technical reports concerning specific systems, prepare Standard Review Plan guidance, prepare inspection guidance, and review license renewal applications.
A preliminary staf f review determined that NEI 95-10 appears to contain the necessary guidance to implement the requirements of 10 CFR Part 54.
Industry participants appear to have effectively implemented the NEI 95-10 guidance for scoping, screening, and identifying intended functions and aging effects consistent with the intent of the License Renewal Rule.
The site visits are being used to assess and identify needed improvements to NEI 95-10 and to determine the level of detail for aging management programs, time-limited aging analyses, and FSA2 supplements.
NEI Presentation Mr. Doug Walters, NEI, outlined the major elements of NEI 95-10.
These are:
e Identifying the
- systems, structures, and. components within the scope of the rule; j
i e
Identifying the intended functions of systems, struc-tures, and components within the scope of the rule;
~
e Identifying the structures and components subject to aging management review; e
Assuring that effects of aging are managed; e
Application of inspections for license renewal; e
Identifying and resolving time-limited aging analyses; e
Identifying and evaluating exemptions containing time-limited aging analyses; e
Identifying a suggested format and content of a license renewal application; and e
Documenting the scoping process, the integrated plant assessment, and the evaluation of the time-limited aging analyses and exemptions.
The NEI 95-10 document also contains (as Appendices) typical structure, component, and commodity groupings and active / passive
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i 432nd ACRS Meeting 4
June 12-14, 1996 4
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determinations for the integrated plant assessment, as well as
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examples to demonstrate the license renewal process.
4 To validate the industry guidelines, NEI is implementing a license renewal demonstration program.
This program will involve seven volunteer sites: Calvert Cliffs, Oconee, Point Beach, North Anna, Oyster Creek, Peach Bottom and Edwin Hatch.
The observations included:
1) while the NEI 95-10 aging management discussion appears to be sufficient, it may need to be bolstered to address j
demonstration;
- 2) the level of detail in the license renewal application and FSAR supplement remains an open topic with the l
staff; and 3) further clarification on timing of time-limited aging i
analyses may be needed.
Other items for consideration are 1
operating experience, consumables, and the Unresolved Safety i
Issue / Generic Safety Issue review process.
1 The current schedule is for the staff to publish the Federal 3
Register Notice regarding the DG-1047 in August 1996, requesting public comments. The industry demonstration program is expected to
)
be completed by the end of October 1996.
The staff is planning to j
hold a public workshop on October 29, 1996 and to publish the final j
Regulatory Guide-1047 by July 1997.
]
1 Conclusion 4
The Committee plans to write a letter to the Executive Director for Operations regarding this matter.
i l
III. Individual Plant Examination Insichts Reoort (Open) 1
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[ Note: Mr.
S.
Duraiswamy was the designated Federal Official for l
this portion of the meeting.]
i Dr. Apostolakis, Chairman of the Subcommittee on Individual Plant 4
Examinations (IPEs), introduced the topic to the Committee and
{
reviewed the discussions of the IPE Subcommittee meeting held June 11-12, 1996.
He noted that the Committee had previously reviewed i
portions of the IPE Insights Report during the 431st meeting of the ACRS, May 23-25, 1996.
He stated that the IPE Insights Report was
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being prepared as a draft NUREG and that the NRC staff planned to have a workshop in January 1997 to discuss the proposed resolution j
of public comments.
J RES Presentation i
i Mr. Mark Cunningham, Chief, Probabilistic Risk Analysis Branch j
(PRAB), RES, and Ms. Mary Drouin, PRAB, RES, led the discussion for the NRC staff.
They introduced their contractors, Mr. Allen Camp i
i l,
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e j.
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432nd ACRS Meeting 5
i June 12-14, 1996 of Sandia National Laboratory and Mr. John Lehner of Brookhaven National Laboratory, who provided supporting discussion.
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The staf f provided an overview of the IPE Insights Report which was 4
developed to gain perspectives on plant designs and vulnerabili-ties.
The perspectives were derived from 75 licensee IPE submit-tals covering 108 operating reactor units.
The staff defined the i
scope of their review, which included consideration of Level 1 and 2 PRA results for full power operation and internal events.
They stated that they did not evaluate the quality of IPEs nor did they consider external events (including fire) or other plant modes such j
as shutdown operations.
i i
The staff summarized the objectives of the program related to i
reactor safety, reactor and containment design, the importance of operator actions, current IPEs as compared with state-of-the-art 1
PRAs, and the Commission's safety goals.
They also considered l
improvements identified as a result of the Station Blackout Rule, and comparison with insights gained from NUREG-1150,
" Severe i
Accident Risks: An Assessment for Five Nuclear Power Plants."
The staff summarized their observations and conclusions for each of the objectives. Significant points made during the discussion include:
l e
Only a few licensees identified vulnerabilities, but all i
identified safety enhancements or plant improvements.
i Most improvements were directed at reducing station i
blackout concerns.
e For BWRs: core damage frequency (CDF) did not decrease for newer BWR designs; CDF variability was primarily due to design / operation differences, modeling assumptions and J
data; and failure to depressurize was the dominant i
contributor to CDF.
a j
e For PWRs: CDF variability was due primarily to plant-specific support system design and operational differenc-es; support system failures were dominant contributors for most plants; and plants with better feed and bleed had lower CDFs.
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e For BWRs: conditional containment failure probability
}
(CCFP) for Mark-I containments had higher early struc-tural failure versus later containments which were largely driven by drywell shell melt-through; bypass and i
containment isolation f ailure was generally not important for BWRs; and the large volumes of Mark-III containments were partially responsible for lower CCFPs.
1 e
For PWRs: CCFP low early structural failure for ice i
condenser containments appeared to be driven by analysis I
432nd ACRS Meeting 6
June 12-14, 1996 assumptions rather than design features; bypass, espe-cially steam generator tube rupture, was important to early structural failure for both ice condensers and large dry and subatmospheric containments; and isolation failures were significant in a number of large dry containments.
Concerns were identified in some IPEs relative to human reliability
- analysis, common-cause
- failures, data analysis, and success criteria. However, Level 1 methods were generally sound.
e Perspectives in IPEs were consistent with NUREG-1150 except that the likelihood of early containment failure was higher for ice condenser PWRs than for large dry containment designs.
Dr. Shack questioned whether most licensees tried to quantify the benefits of improvements and was advised by the staff that most licensees did not.
The staff stated that most assessments were in the form of sensitivity studies.
l Dr. Apostolakis questioned the extent to which uncertainty was considered in the analysis.
This was followed by extensive discussion related to the types of uncertainty that may or may not have been considered (i.e.,
aleatory or epistemic).
The staff stated that most IPEs did not address uncertainty.
The staff also stated that uncertainty is more closely linked with state-of-the-art PRAs and that the IPEs addressed the more narrow scope defined in Generic Letter 88-20.
At the conclusion of the meeting, Dr. Apostolakis summarized his views on the draft IPE Insights Report.
He detailed the schedule for future ACRS reviews and stated that he did not believe a letter would be appropriate at this time.
Conclusion The Committee plans to continue their review of this matter as insights are integrated into NRC programs for risk-informed and performance-based regulation.
IV.
Loss of Offsite Power at Catawba. Unit 2 (Open)
[ Note:
Mr.
S. Duraiswamy was the Designated Federal Official for this portion of the Meeting.)
Introduction
t c
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I ll 432nd ACRS Meeting 7
June 12-14, 1996 Mr. Lindblad, Acting Chairman of the Plant Operations Subcommittee, introduced the topic to the Committee.
He also introduced representatives of the NRC staff and representatives from Duke j
Power Company.
Mr. Lindblad stated that the purpose of this presentation was to brief the Committee on a loss-of-offsite-power (LOOP) event that occurred on February 6, 1996 at Catawba, Unit 2.
j The primary focus of this meeting was on the Special Inspection Team Report (50-413/96-03) findings.
j Mr. Wylie advised the Committee that he had a conflict of interest j
in this aiGd.
l NRC Presentation
)1 Mr. Harold O.
(Chris) Christensen, Chief, Maintenance Branch, DRS, Region II, led the discussions.
Messrs. Edward Goodwin, Acting j
Chief, Events Assessment Branch, NRR, and Mike Tuckman, Senior Vice President, Nuclear Generation, Duke Power, provided supporting discussion.
J l
Significant points made during the discussion were:
Indications of intermittent electrical grounds were not properly analyzed by the control room staf f the day prior to the LOOP event.
e The "2B" emergency diesel generator (EDG) was taken out of service on the morning of the event.
e Two main generator isophase bus potential transformers grounded out, causing a main generator and a reactor trip.
e The indicated electrical fault caused a loss of offsite AC power to Catawba, Unit 2.
With the "2B" EDG out of service, only the "2A" EDG started, thus supplying AC power to the "A" train safeguards equipment.
e The steam generators cooled down, which lowered steam pressure to the safety injection actuation setpoint. The ensuing safety injection increased the water volume in the reactor coolant system, causing the pressurizer to go water solid.
e The pressurizer power-operated relief valve (PORV) cycled approximately 74 times.
The PORV discharge over-pressurized the pressurizer relief tank (PRT), located inside the containment building.
The PRT then relieved into containment, slightly increasing the containment pressure.
1 s
s 432nd ACRS Meeting 8
June 12-14, 1996 l
e A Notification of Unusual Event was declared.
t Full offsite power was restored during the morning of February 11, 1996, e
The root cause of this event was inadequate preventive maintenance of the isophase bus duct.
This allowed moisture and foreign material to build up on the isola-tion bushings, creating an electrical path to ground (short) from the main generator output.
e Duke Power has replaced the potential transformer bushings with an improved design, inspected and repaired
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components, and enhanced the preventive maintenance
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program in this area.
Conclusion t
l This briefing was for information only.
V.
Jssues Associated with Steam Generators (Open)
(Note:
Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.]
Staff Presentation Mr. Jack Strosnider, NRR, noted that the staff met with the Joint i
ACRS Subcommittees on Material & Metallurgy and Severe Accidents on June 3-4, 1996, to discuss steam generator issues.
He provided an overview of the industry experience with steam generator tube degradation mechanisms and explained the reasons for pursuing rulemaking.
Mr. Strosnider outlined the staf f schedule for issuing a revised steam generator rule and the expected interactions with industry.
i Mr. Strosnider explained the desired attributes of a performance-based, risk-informed rule, and the framework for the proposed rulemaking.
He stated that deterministic and probabilistic structural performance criteria are under development.
He explained that the criteria should be measurable, tolerable, enforceable, and able to enbrace new forms of technology.
Mr.
Strosnider used a flow chart to explain the program strategy for assurirg steam generator integrity.
The steam generator rule is intended to maintain defense-in-depth through a balanced use of materials, systems, and radiological controls, as well as inspec-
- tion, leakage monitoring, operator
- training, and emergency operating procedures.
l 432nd ACRS Meeting 9
June 12-14, 1996 Mr. Strosnider concluded the presentation by describing the safety assessment considerations and the unresolved technical issues. The unresolved issues included the risk of tube-induced failures under severe accident conditions, tube response to high temperatures, severe accident thermal hydraulic effects, and analyses of event trees.
Mr. Strosnider and the Committee Members discussed the methods for detecting tube degradation, the quality of data bases used to develop correlations, and the reason for assessing program elements in addition to performance criteria.
They also discussed the importance of relating performance criteria to well defined and technically justified risk levels, and of quantifying the uncer-tainties in risk analyses.
Dr. Catton suggested that accident management concepts, such as flooding the reactor vessel cavity, that would increase the challenge to steam generator tubes, needed to be included in the proposed rule.
Dr. Kress suggested moving guidance for accessing program elements from the regulatory guide to the standard review plan.
Nuclear Enerav Institute (NEI) Presentation Mr. Alexander Marion, NEI, defined risk-based and performance-based regulations.
The proposed framework described by Mr.
Marion included a performance-based rule and a regulatory guide that would endorse industry implementing documents.
The regulatory guide would provide performance criteria for structural integrity, accident leakage, and operational leakage.
The industry document would describe a programmatic approach, condition monitoring, and operational assessments.
Mr.
Marion noted that the NEI and NRC staffs have discussed regulatory guide items to determine whether the items should be performance-based criteria or requirements for programmatic activities.
He stated that NEI planned to develop a white paper on how performance-based and risk-based regulatory approaches relate to the defense-in-depth concept.
Mr. Marion and the Committee Members discussed the meaning of licensee performance, the basis for the limit of 10-2 spontaneous tube ruptures per reactor year, and uncertainties associated with the probability of event sequences.
Conclusion The Committee decided to table a draf t letter until the August 8-9, 1996 ACRS meeting.
432nd ACRS Meeting 10 June 12-14, 1996 VI.
Browns Ferry Nuclear Plant, Unit 3 (Open)
[ Note: Mr.
S. Duraiswamy was the Designated Federal Official for this portion of the meeting.]
Introduction Mr. Wylie, Chairman of the Plant Operations subcommittee, intro-duced the topic to the Committee, and stated that the purpose of this session was to hold discussio7s with the representatives of Tennessee Valley Authority (TVA), the licensee for Browns Ferry Nuclear Plant (BFN) Unit 3, regarding the issues that led to the shutdown of BFN Unit 3 and the corrective actions taken by the licensee prior to restart.
He further stated that this briefing was for information only.
Licensee cresentation Mr. Rick Machon, Vice President, Site Operations, led the discus-sions.
Messrs.
Pedro Salas, Site Licensing Manager and Gene Preston, Plant Manager, provided the supporting discussions.
Backcround Information on the Recovery of BFN Unit 3 Mr. Machon briefly discussed the root causes of BFN problems which led to the shutdown of BFN Unit 3.
Significant points made during the discussion were:
e There was a lack of clear assignment of responsibility and authority to managers and their organizations.
They also lacked clearly established accountability for performance.
There was insufficient management involvement and control of the workplace leading to a failure to adequately establish the highest quality of performance.
They failed to consistently maintain a documented design basis e
for the plant and failed to control the plant's configuration in accordance with that basis.
o Substantial room for improvement was noted in the areas of maintenance and regulatory commitment backlogs and plant material condition.
BFN Units 1, 2,
and 3 were placed on Category 3 of the NRC's watch list (requiring Commission approval prior to restart) in October 1986.
4 432nd ACRS Meeting 11 June 12-14, 1996 Summary of Plant Uoorades Mr. Machon presented briefly the following summary of the plant upgrades and extensive programmatic improvements that were made prior to restart of Units 2 and 3.
e Cable installation (including cable separation) e Design Baseline and Verification Program o
Fire protection upgrades e
Procedure upgrades e
Recirculation system pipe replacement e
Replacement of the majority of electrical components inside the drywell Mr. Machon described the overall effort to recover Unit 2.
This effort involved revision of approximately 1500 engineering calculations, 5200 work plans, over 9 million crafts hours and approximately 14.8 million hours of engineering.
BFN Unit 3 had a similar scope of work for its recovery.
Mr.
Preston briefly presented lessons learned from the Unit 2 recovery, which provided the foundation for Unit 3's recovery.
These lessons were incorporated into the entire recovery effort.
Mr. Preston stated that TVA merged the recovery and operations organization for Unit 3 in the early spring of 1995 as the BFN Unit 3 entered into the testing and operating mode.
At the completion of the testing activity, the site became a single operating organization that included site engineering, recovery engineering, and the plant modification group.
This single operating organiza-tion is managed by a dedicated Assistant Plant Manager.
Conclusion This briefing was for information only.
VII. Health Effects of Low Levels of Ionizino Radiation
[ Note:
Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.]
Introduction Dr. Thomas Kress, Vice-Chairman of the Joint ACRS/ACNW Subcommit-tee, noted that the written comments received from two private
432nd ACRS Meeting 12 June 12-14, 1996 citizens, Mr. Theodore Rockwell and Mr. Al Tschaeche, had been distributed to all Members.
He stated that the following presenta-tions would repeat some of the information heard by the Subcommit-tee on March 26, 1996.
NRC Staff Presentation Dr.
John Glenn,
- NMSS, differentiated between the scientific development and regulatory use of the linear quadratic model of the health effects of low levels of ionizing radiation.
He explained that scientific models are developed using existing data and are subject to peer review, while regulations are developed based on nationally and internationally accepted models, and on the need to balance the risks and benefits of using radioactive materials.
Dr.
Glenn stated that NRC is funding a study by the National Council on Radiation Protection and Measurements (NCRP) to assess the scientific bases for the present linear quadratic model.
Similar-ly, the Interagency Steering Committee on Radiation Standards is funding a study by the National Academy of Sciences to determine the need for forming a BIER VII Committee.
Dr. Glenn and the Committee discussed other government agencies that set radiation standards, the risk standard used in developing regulations, and the basis for the staff regulatory limits.
They discussed the composition and selection of members for the NCRP Study and the role of the group advisor.
NRC Visitino Medical Fellow Presentation Dr. Myron Pollycove, NRC Visiting Medical Fellow, explained the biology associated with somatic mutation-causing cancers.
He presented the results of ucientific studies concerning radium malignancies, lung and breast cancers, atomic bomb survivors, and nuclear shipyard workers.
He concluded that proper evaluation of the data from the studies demonstrates a hormetic effect in response to low levels of radiation.
He expressed the opinion that scientific data that did not confirm the linear, no-threshold (LNT) hypothesis had been overlooked or suppressed by some professional health physics societies and organizations.
Dr.
Pollycove explained the mechanism for radiation damage in mammalian cells, and the different cell repair mechanisms.
He discussed the reasons for the difference in responsiveness of cell repair mechanisms at high and low radiation doses.
To support the existence of repair mechanisms, Dr. Pollycove presented the results of research studies on basal cell carcinoma, mouse splenic cells, and low dose radiotherapy of non-Hodgkins lymphoma.
He explained how Mulgavkhar's model describing lung carcinogenesis induced by radon was improved by including the effect of the stimulation of repair mechanisms by low radiation doses.
432nd ACRS Meeting 13 June 12-14, 1996 Dr.
Pollycove and the Committee discussed cancers caused by mechanisms other then radiation, statistical methods used to fit a curve to research data, and the uncertainty associated with the data.
Invited Excert Presentation Dr.
Marvin
- Goldman, Professor of Surgical and Radiological Sciences, University of California, Davis, and current President of the Health Physics Society, stated that risk assessments and regulations must be based on sound science.
He explained the origins of the LNT hypothesis and expressed the opinion that the hypothesis should be reexamined.
Dr. Goldman noted that the LNT hypothesis was based on the assumption that high radiation dose effects can be extrapolated to low radiation dose effects.
He presented the following studies, which do not support the assump-tion:
animal studies, radiation treatment of men for ankylose enspondylitis in e
the 1940's, radiation therapy of women for cervical cancer, e
health effects data for the civilian populations living e
downstream of two plutonium production facilities in Russian, and health effects data for populations living downwind of the Chernobyl accident.
Dr. Goldman stated that he believed in the hormetic effect of radiation, but was not convinced that hormesis is beneficial in terms of cancer risk.
He warned that confounding factors must be carefully considered when reviewing data.
He noted that when science is able to reduce the uncertainties associated with research studies, then regulators would be able.to rely on less conservative models.
Dr. Goldman concluded that it was ridiculous to use collective dose as a means of determining risk.
Dr. Goldman noted that the NCRP, as an organization, was the primary author of the LNT hypothesis.
He left open the question of whether the NCRP could be objective in reexamining the LNT hypothesis.
Dr. Goldman concluded that neither the NCRP structure nor internal works should be impeded.
Dr. Goldman and the Committee Members discussed the effect of the political process on regulations, the difference between the regulatory and scientific model, the reason studies are not conducted on the effects of low levels of radiation, and the diversity of the specialists on the NCRP working group.
I
j 432nd ACRS Meeting 14 June 12-14, 1996 Private Citizen Presentation l
Dr. Theodore Rockwell, private citizen, stated that the use of the LNT hypothesis in the regulatory process was costing lives and tremendous amounts of money.
He provided the following examples:
After the Chernobyl accident, upward of 100,000 women chose to have abortions based on the fear of delivering deformed babies, i
Consumer groups recommend removing fire detectors because "no amount of radiation is harmless."
The estimated cost of returning contaminated sites to background conditions is expensive, while there are no proven health benefits.
Dr. Rockwell, Dr. Goldman, and the Committee Members discussed the origins, official standing, and selection process of the NCRP.
They also discussed the relationship of NCRP recommendations to regulatory decisions.
Cone.tusion Based on the information briefing, the Committee decided not to participate in the report prepared by the ACNW concerning this matter.
VIII. EXECUTIVE SESSION (Open)
[ Note:
Dr. J. Larkins was the Designated Federal Official for this portion of the meeting.]
A.
Reports, Letters and Memoranda Severe Accident Research (Report to Shirley Ann Jackson, Chairman, NRC, f rom T. S. Kress, Chairman, ACRS, dated June 28, 1996.)
Draft Reculatorv Guide DG-1047,
" Standard Format and Content for Aeolications to Renew Nuclear Power Plant Operatina Licenses" (Letter to James M. Taylor, Execu-tive Director for Operations, from T.S. Kress, Chairman, ACRS, dated June 18, 1996)
B.
Reconciliation of ACRS Comments and Recommendations
[ Note:
Mr. S. Duraiswamy was the Designated Federal Official for this portion of the meeting.]
3 '.
i 4
5 432nd ACRS Meeting 15 4
June 12-14, 1996 The Committee discussed the response from the NRC Executive Director for Operations to ACRS comments and recommendations included in recent ACRS reports:
EDO letter dated May 24, 1996, responding to the ACRS report dated April 22, 1996, ccncerning the Proposed Revisions to 10 CFR Parts 50 and 100 and Proposed j
Regulatory Guides Relating to Reactor Site Criteria.
The Committee decided that it was satisfied with the EDO 4
response.
j J
LETTER FROM CHAIRMAN JACKSON l
i The Committee discussed a letter from Chairman Jackson dated i
June 3, 1996, responding to ACRS comments and recommendations included in the ACRS report dated April 23, 1996, concerning Probabilistic Risk Assessment Framework, Pilot Applications, and Next Steps to Expand the Use of PRA in the Regulatory l
Decision-Making Process.
The Committee plans to continue its review of issues associat-i j
ed with risk-informed and performance-based regulations.
Also, the Committee plans to look at the emerging policy
)
issues identified in the May 15, 1996 Staff Requirements Memorandum and provide recommendations to the Commission.
C.
Report on the Meeting of the Planning and Procedures l
Subcommittee (Open) l The Committee heard a report from Dr. Kress on the Planning and Procedures Subcommittee meeting held on Jane 10, 1996.
l The following items were discussed:
i l
1.
OUADRIPARTITE MEETING j
A letter has been sent to the Japanese Nuclear Safety i
Commission (with copies sent to the Germans and French) referring to a fall 1997 Quadripartite Meeting, including i
proposed agenda items for them to consider.
I RECOMMENDATION The Subcommittee recommends that the Committee wait for a reply from the Japanese Safety Commission before i
proceeding any further.
It was mentioned that the agenda l
may dictate which ACRS members attend this meeting.
1
a.
j j
432nd ACRS Meeting 16 June 12-14, 1996 2.
DEPARTMENT OF ENERGY /NRC MEMORANDUM OF UNDERSTAND-ING (MOU) l The NRC and DOE have signed an MOU to establish the i
protocol (basis for review and consultation) with respect to possible DOE acquisition of commercial light-water I
reactors for tritium production.
The NRC would have to j
review and license such a facility and process.
1
{
RECOMMENDATION This material was provided for information only.
1 3.
ACRS RETREAT j
A retreat for ACRS Members and ACRS Senior Management.is being scheduled for October 17-18, 1996 in Annapolis, Maryland.
Dr. Seale has been assigned the responsibility i
for developing an agenda for the retreat and assignments for the Members.
Hotel accommodations are being sought.
1 RECOMMENDATION The Committee had previously agreed to a retreat in September 1996, but there were no accommodations avail-able at that time in Annapolis or Baltimore.
Every ACRS member was polled on alternative dates and, except for 4
i one member, the dates of October 17-18, 1996, were agreed f
to.
I
)
Dr. Kress suggested that the agenda be limited to only a j
few (2 or 3 at most) items, such as Regulatory Philosophy i
and ACRS Activities, with several subtopics.
Dr. Kress proposed that members suggest subissues and develop a strawman position to establish the points of discussion.
Dr. Larkins suggested that the Committee take a look at the Bylaws again.
Issues proposed for discussion should be forwarded to Dr. Seale prior to the August 1996 Full Committee meeting.
4.
SUMMER EMPLOYEES Three new summer employees have joined or will be joining the ACRS/ACNW staf f.
Ms. Cindy Hsu and Ms. Chris Lootens have worked for ACRS previously.
[The third employee was later withdrawn.]
O 8
432nd ACRS Meeting 17 June 12-14, 1996 RECOMMENDATION This material was provided for information only.
5.
IMPLEMENTATION OF CWS PILOT PROGRAM The Of fice of Personnel approved for one year the request by the Executive Director, ACRS/ACNW, to implement a compressed work schedule (CWS) pilot program.
This program will provide the staft more flexibility in scheduling their hours during the pay periods in which Full Committee meetings occur.
Under the CWS pilot program, staff members have the option to schedule their hours to coincide with the extended weekday and Saturday hours on which the Committees meet, so that they are paid for the actual hours worked.
Participation in t program should alleviate the regular and recurring unp,his aid overtime worked by engineers and staff scientists.
To implement the program, the ACRS staff negotiated with the union that future ACRS and ACNW Full Committee meetings would be scheduled during the first week of the pay period, where practicable.
RECOMMENDATION Dr. Kress and Dr. Shack thought this was a good idea.
Dr. Larkins said it was not final yet, and that there would be another meeting with the union.
He also men-tioned that there were a lot of restrictions such as not splitting pay periods.
To the extent practical, meetings should be scheduled for the first full week of the month so we can meet this criteria.
This will prohibit us from changing meeting dates once they are set.
6.
CONSULTANT PERFORMANCE EVALUATION To provide enhanced accountability on the use of consul-tants, a systematic process should be established for evaluating the performance of ACRS consultants.
As a follow-on to each Subcommittee meeting, a written evalu-ation would be made of the consultant's performance at the meeting and the quality of the consultant's reporcs.
This would be based on the input from members partici-pating in the meeting.
RECOMMENDATION It was suggested that a form be developed.
Dr. Kress thought it should be signed by the Subcommittee Chairman,
432nd ACRS Meeting 18 June 12-14, 1996 who can solicit comments from the Subcommittee Members if so desired.
He also wanted to know who would be respon-sible for f;Hing the form out and getting it aigned.
Dr. Larkins thought the engineer could do this.
Dr.
Kress did not believe that this was an appropriate function for the engineers and that only the Members were qualified to make such assessments.
This process could help determine which consultants the Committee should continue using and would provide greater accountability.
7.
DINNER WITH CHAIRMAN JACKSON Chairman Jackson invited Drs. Kress, Catton, Apostolakis and Larkins to a dinner meeting on June 11, 1996.
RECOMMENDATION Information will be provided to the Committee during the meeting.
8.
TRAVEL A request was received from Dr. Catton to attend an international meeting in Park City, Utah, where he will be giving a paper on lower cavity flooding.
RECOMMENDATION The Subcommittee recommended that the travel request be approved.
9.
MEMBERS' ISSUES e
In a recent memorandum, Mr.
Carroll recommended that the Committee streamline its discussion of administrative and procedural matters and spend more time on policy issues and strategic planning.
In a second memorandum, Mr. Carroll commented on the memos from Dr. Powers concerning the health ef-fects of low levels of ionizing radiation.
e Mr.
Lindblad requested that the ACRS Executive Director confer with the Office of the General Counsel on whether there is a statutory requirement for the ACRS to review the design changes submitted by General Electric for the ABWR design.
Mr.
Martin Malsch, Deputy General Counsel for the NRC, noted in a conversation that, in his opinion, a statutory requirement exists, particularly if the
5, 432nd ACRS Meeting 19 June 12-14, 1996 changes are safety significant.
Subsequently, the Commission has, as part of the SRM on the recent meeting with the ACRS, requested the Committee to review GENE's recent submittal containing safety-significant design changes prior to a Commission briefing on this subject in August 1996.
e Mr. Lindblad's comments on the issue of the pro-posed joint letter with the ACNW were reviewed.
RECOMMENDATION Regarding the first item, the Planning and Procedures
{
Subcommittee found that, while the May meeting was an unusual meeting, some of Mr.
Carroll's comments on streamlining the prolonged discussions were reasonable.
It was generally agreed that a firm meeting schedule should be established in October or November for the coming year and not be changed.
The ACRS should vote on whether there is enough support to have a joint letter on the health effects of low-level radiation.
Also there should be a discussion of a joint letter where the Committee had additional comments.
Regarding the third item, the Planning and Procedures Subcommittee felt that the issue had been addressed.
D.
Future Meetina Acenda Appendix IV summarizes the proposed items endorsed by the Committee for the 433rd ACRS Meeting, August 8-10, 1996.
The 432nd ACRS meeting was adjourned at 5:55 p.m. on Friday, June 14, 1996.
~'
APPENDIX I i
Fnered Eagletor / Vol 61. No.108 / Tuesday, June 4,1996 / Noticas 28M9 Washington, D.C. 30644:Telepheme NRC incorporates condidons in b 4.N hu m g g g f4 umber: (202) 273-1812.
SNM licanoe which provide NRC the the uest for a hearing is timely in l
Sesem lemmem4emkha, latitude to enform b Agreement State with $ 2.1205(c).
DuPuty Couneef h-conditions,if NRC detsemines in accordance with to CFR (FR Doc. 96-13837 Fund 6-MGBt 4:45 mm) such action is n
. Finally, the
$ 2.1205(e), each request for a hearing NRC limnos does not rogate or must also be served, by delivering it l
same ones mes as-,
- = inia the authority of the State personally or by mall. to:
governed by its agreement under section
- 1. N applicant, Chem-Nuclear NUCLEAR REOULATORY 274b of the Atomic Energy Act of 1954, Systems, Inc.,140 Stoneridge Drive, COtmeSalOeg as amended, with NRC, to regulate, Columbia, South Carolina 29210, inspect or otherwise exercise contml of Attention: Mr. William B. House, and*-
(DecheHea 27-47) operations, with respect to the source
- 2. N NRC staff, by delivery to the and byproduct material, for disposal of Executive Disctor for Operations, One i
Considere#on of Appuoseon W that meterial at the LLW disposal White Flint North,11555 Rockville Renewel of a Lloonee To Despose of facility at Bamwell, South Carolina.
Pike, Rockville, MD 20852, or by mail, W
RedosoWre Weste Prior to the issuance of the proposed addressed to the Executive Director for Contineng aponeet h M W renewal NRC will ha a made Endings Operations. U.S. Nuclear Regulatory required by the Atomic Energy Act of Commission, Washington, DC 20555.
t 1954, as amended, and NRCs For further details with respect to this acescv: Nuclear Regulatory regulations. Neo Andings will be acd a, the application for amendment Commission.
d-aaa*=d in a Safety Evaluation request is available for inspection at the i
acnose: Notice of consideration of an Report and an Environmental NRC's Public Document Room. 2120 L Assessment.
StmW, Washington, DC 20555.
application for renewal of a llanes to
" " " N C " CU l
dispose of low-level radioactive weste b NRC provides notias that this is conuinint'special nuclear material by a proceeding on an a lication for a Enothy E. Harris,14w-Imvel Weste and 4
Chem-Nuclear Systems, Inc., and license amendment within the
=,seloning Projects Branch, opportunity for a hearing.
scope of Subpart L " Informal Hearing Division of Waste Management, OfBce i
Promdures for Adjudication in of Nuclear Material Safety and i
N Nuclear Regulatory Commission Materials I la a-ia= Pmonodings," of Safeguards U.S. Nuclear Regulatory (NRC)is considering b renewal of NRC's rules and r"actico for domestic Commission, Washington, D.C. 20555.
(
Telephone: (301) 415-6613. Fax.: (301) 1 License No. 12-13536-01, his license licensing p ings in 10 CFR Part 2.
415-5396.
l is issued to Chem Nuclear Systema, lac, Pursuant to $ 2.1205(a), any person (CNSU for the disposal of wastes whose interest ma be affected by this Deted at Rockville, Maryland, this 28th day containing special nuclear material proceeding may a request for a of May,1996.
(SNM)in the low level radioactive hearing in with $ 2.1205(c).
For the Nuclear Regulatory Commisnon.
j waste (LLW) disposal fedlity, located A request for a hearing must be filed Eshort A.Neleen, l
near Barnwell, South Carolina. NRC within thirty (30) days of the date of Acting Chef. low-Zeel waare and
'J licenses this facility under 10 CFR Part publication of this Federal Register Decommissionmg Profects Branch. Dmsson
- 70. The license renewal application was notice.
of wasesManagement orxwo/ Nuclear Marano eryanWeguards.
submitted on April 10,1996.
b request for a hearing must be In Doc. 96-13877 Filed 6+96; 8.45 aml i
N LLW disposal facility located filed with the OfBm of the Secstary j
near Barnwell, South Carolina, is either:
ausse ones nos.ei-e licensed by the State of South Camlina
- 1. By delive to the Docketing and for disposal of source and byproduct Service ranch of the Secretary at One * "Advloory Committee on Reactor material. The NRC license allows the Whl F
,F*ir Safeguarda; tesseing Notice disposal of SNM, and acknowledges that Pb I
2 2
the State's regulated activities consutute
- 2. By mail or telegram addressed to To carry out the responsibilities set I
the major site activities. As a muh, the Secmtary, U.S. Nuclear Regulatory forth in Sections 29 and 182b. of the NRC relies extensively on the State s Comminaion. Washington, DC 20555.
Atomic Energy Act (42 U.S.C. 2039, mgu ator mgram to hte b Attention: Docketing and Service 2232b), the Advisory Committee on facility an licensee e cogehelity to Branch Reactor Safeguards will hold a meeting demonstrate reasonab4p that on June 12-14,1996, in Confomm the disposal of LLW In addition to meetin8 other Room T-283 11545 Rockville Pike' accomplished safely. MHWs end, NRC applicable requimments of 10 CFR Part Rockville, Maryland. & date of this coordinates the review and assamament 2 of the NRC's regulations, a request for g
of the license with the State of South a hearing filed by a person other than 6
W de Carolina Department of Health and an applicant must describe m detail:
November 27,1995 (60 FR 58393).
Envimnmental Control. To avoid a
- 1. The interest of the requester in the du plicate effort, NRC has identified pra m Aina-Wednesday, Jane 12, t eos several areas in which it relies primarily
- 2. How that interest may be affected 100 P.M. :15 P.M.: Opeaing on the State regulatory program. Areas by the results of the proceeding, Remarks by the ACRS Chairman distinct to SNM regulation are directly including the reasons why the requestor (Open)-The ACRS Chairman will make evaluated by NRC. Under the NRC should be permitted a hearing, with opening remarks regarding conduct of license, several State identified license particular reference to the factors set out the meeting and comment briefly conditions are referenced. This in 5 2.1205(g);
regarding items of current interest.
appmach ensures that NRC is aware of
- 3. The requestor's areas of concern During this session, the Committee will significant licensee activities requiring about the licensing activity that is the discuss priorities for preparation of State regulatory action. Additionally, subject matter of the proceeding; and ACRS reports.
~
e 28290 Federal Register / Vol. 61, No.108 / Tuesday, Juns 4,1996 / Notices 1:15 P.M.-2:45 PR: Draft Regulatory opening remarks reprding moduct of with h use of potassium iodide after j ~
Guide, DG-1047, " Standard Format aarl the meeting.
a severe acx:ident and the potential risk Content for Appilaations so nonew
- 35 AM-9:30 AM:Essues assodated with the une of potassium Nuclear Power Plant Openting Assocsated with Steam Genemtors Lodide.
Licenses"(Open)-The C=mittee will (Open)-ne Committee will hear Reprwentatives of the nuclear hear presentations by and hold presentations by and hold discussions industry will participate. as appropriate.
discussions with representatives of the with representatives of the NRC staff 22:45 P.M.-6.00 PX: Prepamtion of NRC staff regarding the draft Regulatory regarding issues associated with steam ACRS Repons (Open)-N Committee Guide, DG-1047.
generators. Also, briefing by and will continue discussion of proposed Representatives of the nuclear discuuions with reprentives of the ACRS reports on matters considered 4
industry will partidpete, as appropriate. Nuclear Energy Institute regarding the during this meeting was well as a 2:45 P14-3:45 PM:IPEInsights MAAP Code, proposed ACRS report on Severs 4
lleport (OpenHN Committee will Representatives of other interested Accident Research.
bear presentations by and hold Parties will partidpete, as appropriate.
Pmoedures ist the conduct of and 9:30 AM-!!:00 AX: Browns Perry partid to ACRS meetings were discussions with representatives of the Nuclear Plant, Unit J {Open)--N publi in & Mi Register on NRC staff and its contractors regarding the Individual Plant Pramtnation (IPE)
Committee will hear presentations by Sepensaber 27..
too FR 49925). In and hold discussions with accordance with pmcedures, oral Insights Report.
f*Presentatives of the licensee or written statements may be presented Representatives of the nuclear (Tennessee Valley Authority) and the by members of the public, electronic industry will partidpete, as appropriate. NRC staff regarding issues tnat led to the recordings will be permitted only 4:00 FX-5.00 PM: loss of site shutdown of Browns Ferry Unit 3 and during the open portions of the meeting, Power at Catawba, Unit 2(Open ne the corrective actions taken by b an entions may be aske(only by Committee will hear presentations by m
of the Committee,its liconew prior to restart.
and hold discussions with 11:25 AM-12:30 AR:Reconcillation mneultants, and staff. Persons desiring i
representatives of the NRC staff of ACRS Comments and to make oral statements aboul ! notify Recommendations (Open)-%e Mr. Sam Duraiswamy, Chief Nuclear regarding the findin and recommendations o the NRC Special e-mittee will discuss responses imm Reactors Branch, at least five days Inspection Team which investigated the the NRC Executive Director for before the meeting, if possible, so that lost of offsite power event that occurred Operations (EDO) to comments and appmeriate arrangements can be made I
on February 6,1996 at the Catawba recommendations included in recent to allow b necauary time during the Nuclear Plant Unit 2 AGS F' Pats, including the EDO meeting for such statements. Use of still, l
Representatives of the licensee will response to the April 22,1996 ACRS motion icture, and television cameras F* Port on Pmpoemd Mons 210 GR W mW may b MM to
-5:
P. uture ACRS Parts 50 and 100 and Peposed select ed portions of the meeting as Activities (OpenHN Comm.ttee will Regulatory Guides Relating to Reactor determined by the Chairman i
Information regarding the time to be set discuss recommendations of the Site Criteria.
Planning and Procedune Subcommittee 23:30 PR-7:00 PR: Prepamtion of aside for this purpose may be obtained mgarding i,tems proposed for ACHS Reports (Open)-The Committee by matacting the Chief of the Nuclear l
consideration by the full Committee will continue discussion of proposed Ranctors Bronch prior to the meeting. In during future meetings.
ACRS mports on matters considered view of the possibility that the schedule for ACRS meetings may be adjusted by 5:30 P.M.-6:15 PM: Report of the during this meeting as well as a the Chainnan as necessary to facilitate Planning and Procedures Subcomtnittee proposed ACRS report on Severe the mnduct of the inesting, persons (Open/ClosedHThe Committee will Acrident Research hear a report of the Planning and planning to attend should check with Pmcedures Subcommittee on matters Friday, June 14,1996 the Chief of the Nuclear Reactors Branch related to the conduct of ACRS 8:30 a.m.-d:35 a.m.: Opening if such reacheduling would result in business, and organizational and Remarks by the ACRS Chairman major inconvenience.
in acrordance with Subsection 10(d) personnel matters relating to the ACRS (Open)-N ACRS Chairman will make staff-opening remarks regarding conduct of P.L 92-463,I have determined that it is necessary to close portions of this A portion of this asesion may be b ramting.
closed to discuse organi=tional and 8:35 a.m.-1020 a.m.: Health Effects of meeting noted above to discum matters personnel matters that relate solely to Iow.I,vels oflonizing Radiation that relate solely to the internal the internal personnelrules and (Open)-b Committw will hear personnel rules and practices of this practices of this Advisory Committee, preantations by and hold discussions Advisory Committee per 5 U.S.C.
and matters the release of which would with reprwentatives of b NRC staff, 552h(c)(2), and to discuss matters the constitute a clearly unwarranted Health Physics Society, and invited release of which would constitute a invasion of personal privacy.
experts regarding the health effects of clearly unwarnated invasion of 6:25 P.M.-720 PM:Preparution of low levels of ionizing redistion.
personal privacy per 5 U.S.C. 552b(c)(6).
ACRS Reports (Open)-The Committee Representatives of the nuclear Further information regarding topics will discuss proposed ACRS reports on industry and other interested parties to be discussed, whether the meetmg matters considered dunng this meeting will participate, as appropriate, has been cancelled or rescheduled, the as well as a proposed ACRS report on 10:15 AM-II:45 A.M.:NRCPolicy Chairman's ruling on requests for the Severe Accident Rasearch Regarding the Use of Potassium lodide opportunity to present oral statements offer a Severe Accident (Open)-The and the time allotted therefor rars be Thuredsy, June 13,1996 Committee will bear prwentations by obtained by contacting Mr. Sam 8:30 AM-8:35 A.M.: Opening and hold discussions with Duraiswamy, Chief. Nuclear Reectors Remarks by the ACRS Chairman representatives of the NRC staff Branch (telephone 301/415-7364).
(Open)-N ACRS Chairman will make regarding b NRC policy associated between 7:30 AM and 4:15 PM EI7T.
Federal Registee / Vol. 61, No.108 / Tuesday, June 4,1996 / Notices 28251 l
ACRS meeting notices, snesting longer wish to receive it, or would like Office of PersonnelManagement transcnpts, and letter reports aus snow to be added to it, please contact the Not to exmed 500 positions in Federal available on FedWorld frons the "NRC Office of the Secretary, Attn: Operations nnad a e tm t be Med MAIN MENU." Direct Dial Aumess Brench. Washington, D.C. 20555 (301-a cmunun@utmach number to FedWorld is (8001883-9672:
415-1963).
the local direct dial number is 703-321-In addition, distribution of this Inf nnaum Netwak Pmgram EHective
=
A ril 11,1996.
P 3339.
meeting notice over the internet system The 433rd ACRS meeting will be held is available. If you are interested in Department of State on August 8-10,1996.
receiving this Commission meeting Dated: May 29.1996.
schedule electmnically, please send an Intemational Boundary Commission U.S. and Canada Andrew L. Bates, electmnic message to alb@ntc. gov or j
gktenic. gov.
Temporary and interm,ttent field i
Advisory Commerree Mona8ement Officer.
employees such as mstrumentmen, IFR Doc. 94-13872 Filed 6-3-96; 8 45 aral foremen, recorders, packers, cooks, and 1
,ggg SECY Tracking OffYcer Office of the
- "********0'00"" "8 Secretary.
days within any I calendar year.
Effective April 15,1996.
Sunshine Act Meeting IFR Doc. 96-14107 Piled F31-96; 2:46 pml Aosecy HOLoweo THE usETudo: Nuclear Rrgulatory Commission.
U.S. rnae Guard DATE: Weeks of June 3,10,17, and 24 OFFICE OF PEftSONNEL Not to ermed 25 positions of Marine 1996.
MANAGEMENT Traffic Controllers (Pilot), at grade GS-PLACE: Commissioners' Conference 11 and below for temporary, Room,11555 Rockville Pike Rockville, Excepted Servloe intermittent, or seasonal employment in Miryland' the State of Louisiana. Effective April Ao sect: Office of Personnel status: Public and Closed.
26,1996' Management.
MATTERS TO BE CON 880ERED*.
ACTION: Notics.
FedemlHighmry Administmtion
[U" as MARY:' Ilia gives notice of ositions l
Thursday, /une 6 placed or revoked under les A na H g way Adanhum at 3.30 p m.-Affirmation Session (PUBUC and B. and P aced under Schedule C in grades not higher than GS-5 for l
MEETINC)(if needed) the e.xcepted sornon, as required by subprofessional engineering side work W,eek of /une to--Tenrafr**
Civil Service Rule VI. Exceptions from on highway surveys and construction Wednesday. /une 12 the Competitive Service.
projects. Effective April 26,1996.
3 00 p m.-Bnefing on Part 100 P1nal Rule FOR FURTHEA prORalATION CONTACT:
on Reactor Site Critena (PUBUC Patncia Paige,(202) 606-0830.
Schedule 8 MEETING) iContact: Charles Ader, 301-SUPPlanAEP(TARY INFORhaAT10N: The Office One Schedule B authority was 4 3g p \\622 415-ff rmation Session (PUBUC Personnel Management published its established:
no u a m 8 MEETING)lif needed)
Department of Vetemns Affairs n er week of /une !?-Tentauve the Excepted Service provisions of 5 Not to exceed 25 CriminalInvestigator Tuesday. /une 18 CFR part 213 on May 3,1996 (61 FR (Undercover) positions, GS 1811, in 10 00 a m -Briefing on Status of NRC 19963). Individual authorities grades 5 th*ough 12, conducting Operator Licensing initial Exammauon established or revoked under Schedules undercover investigations in the Pdot Process (PUBLIC MEfflNG)
A and B and established under Veterons Health Administration (Contact. Stuart Richards. 301-41 9 Schedule C during the period. April 1, supervised by the VA, Office of 1 30 a m -Affirmation Session (PUBUC 1996, through April 31,19%, appear in Inspector General. Initial appointments MEETINGl(if needed) the listing below. An established shall be greater than 1 year, but not Schedule B authority not previously exceed 4 years and may be extended aeek of /une 24-Tentative recorded for March 1996 is also listed indefinitely in 1 year incmments.
Tuesd;v. /une 25 below. Future notices wiH be published Effective March 28,1996.
dn fe aCl s
as soon a pOs 4 e fl A Wednesdav. /une 26
~
consolidated listiojt of all authorities as The following Schedule C authorities 1130 a m -Affirmation Session (PUBUC of June 30 will alsd be published.
were established in Apnl 1996:
MEETING)(if needed) 2 JO p m -Meeting with Advisory Schedule A DePutment of AgncWtum Committee on Nuclear Waste ( ACNW)
No Schedule A authorities war, Confidential Assistant to the established in April 1996.
Admimstrator, Food and Nutrition
- The schedule fa cornmission The following Scheduis A authonties Service. Effective Apnl 10,19%.
meetings is submct to change on short were revoked:
Confidential Assistant to the notice. Ta verify the status of meetings Adtninistrator, Animal and Plant Health
- all (recording)-(301) 415-1292.
Nationallobor Relations Boord Inspection Service. Effective Apnl 18, fontact person for more information:
Election Examiners for temporary, 1996.
Bill Hill (301) 415-1661.
part-time, or intermittent employment Confidential Assistant to the in connection with elections under the Administrator, Food and Safety This notice is distnbuted by mail to Labor-Management Relations Act.
Inspection Service. Effective April 24, everal hundred subscnbers;if you no Effective Apnl 15,1996, 1996.
APPENDIX II y [pua-n UNITED STATES NUCLEAR REGULATORY COMMISSION
{
,E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o,
j WASHINGTON, D. C. 20555 f
REVISED June 10, 1996 SCHEDULE AND OUTLINE FOR DISCUSSION 432nd ACRS MEETING JUNE 12-14, 1996 Wednesday, June 12, 1996, Conference Room 2B3. Two White Flint North.
Rockville, Maryland j
1:Of 1:1A P.M.
1)
Ooening Remarks by the ACRS Chairman (Open) 1.3)
Opening Statement (TSK/SD) 1.2)
Items of Current Interest (TSK/JTL/SD) i 1.3)
Priorities for Preparation of ACRS Reports (TSK/SD) o
.2, 2) 1:15 2 : 4)!I P. M.
Draft Reculatorv Guide. DG-1047, " Standard Format and Content for Acolications to Renew Nuclear Power Plant Ooeratina
~
Licenses" (Open) (MHF/MME) 2.1)
Remarks by the Subcommittee Chairman 2.2)
Briefing by and discussions with representatives of the NRC staff regarding the draft Regulatory Guide, DG-1047.
Representatives of the nuclear industry will l
participate, as appropriate.
J 3) 2:45 3:[5P.M.
IPE Insichts Report (Open) (GA/MTM) 3.1)
Remarks by the Subcommittee Chairman 3.2)
Briefing by and discussions with representatives of the NRC staff regarding the Individual Plant Examination (IPE) Insights Report.
Representatives of the nuclear industry will participate, as appropriate.
T 3: 5 4:h0 P.M.
BREAK
{
(rn,ca,ao aa,,.a a ~ nur~.
2 j
ob 4) 4:00 5:00 P.M.
Loss of Offsite Power at Catawba. Unit 2 l
(Open) (WJL/PAB/BH) 4.1)
Remarks by the Acting Subcommittee Chairman 4.2)
Briefing by and discussions with representatives of the NRC staff regarding the findings and recommendations of the NRC Special Inspection Team which investigated the lost of offsite power event that occurred on February 6, 1996 at the Catawba Nuclear Plant, Unit 2.
Representatives of the licensee will participate, as appropriate.
N 5) 5:00 5:30 P.M.
Future ACRS Activities (Open) (TSK/SD) i Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.
6) 5:30 6:15 P.M.
Recort of the Planning and Procedures Subcommittee (Open/ Closed) (TSK/JTL)
Report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business, and organizational and personnel matters relating to the ACRS staff.
(Note:
A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory Committee, and matters the j
release of which would constitute a clearly J
unwarranted invasion of personal privacy.]
I I
7) 6:15 7:OfP.M.
Ergearation of ACRS Reoorts (Open)
Discussion of proposed ACRS reports on:
1 I
7.1)
Severe Accident Research (MHF/NFD) 7.2)
Draft Regulatory Guide Associated with the License Renewal Rule (MHF/MME) i i
l 1
3 Thursday, June 13, 1996, Conference Room 253. Two White Flint North.
Rockville. Marvingd
)
l 8) 8:30 8:35 A.M.
Ocenina Remarks by the ACRS Chairman (Open) 1 (TSK/SD) 9)
8:35 9:30 A.M.
Issues Associated with Steam Generators (Open) (RLS/NFD/BH)
I 9.1)
Remarks by the Acting Subcommittee Chairman l
9.2)
Briefing by and discussions with representatives of the NRC staff l
regarding issues associated with the steam generators.
Also, briefing by and discussions with representatives of the Nuclear Energy Institute regarding the MAAP Code.
Representatives of other interested parties will participate, as appropriate.
l l
10) 9:30 - 11:00 A.M.
Browns Ferry Nuclear Plant. Unit 3 (Open) l (CJW/AS) 10.1)
Remarks by the Subcommittee Chairman 10.2)
Briefing by and discussions with representatives of the licensee (Tennessee Valley Authority) and the NRC staff regarding issues that led to the shutdown of Browns Ferry Unit l
3, and the corrective actions taken by the licensee prior to restart.
3 11:00 11:15 A.M.
BREAK 11:30 A.M.
Reconciliation of ACRS Comments and
- 11) 11:15 Recommendations (Open) (TSK, et al./SD, et al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports.
12:30 P.M.
LUNCH 11:30
4
- 12) 12:30 7:00 P.M.
Precaration of ACRS Recorts (Open)
(3:00 - 3:15 BREAK)
Discussion of proposed ACRS reports on:
12.1)
Severe Accident Research (MHF/NFD) 12.2)
Draft Regulatory Guide Associated with the License Renewal Rule (MHF/MNE) 12.3)
IPE Insights Report (GA/MTM) l 12.4)
Steam Generator Tube Issues (RLS/NFD/BH)
Friday, June 14, 1996. Conference Room 2B3. Two White Flint North.
Rockville Marvisad
/
13) 8:30 8:35 A.M.~
Oceninc Remarks by the ACRS Chairman (Open)
(TSK/SD)
- 1:ot 14) 8:35
- k&tOO A.M.
Health Effects of Low-Levels of Ionizing Radiation (Open) (TSK/NFD) 14.1)
Remarks by the Subcommittee Chairman 14.2)
Briefing by and discussions with representatives of the NRC staff, Health Physics Society, and invited experts regarding the health effects of low-levels of ionizing radiation.
Representatives of the nuclear industry and other interested parties will participate, as appropriate.
ii:oo 10:y, Lte
- 1 M A.M.
BREAK
- 15) 1ede
- 12:02 Neon Preparation of ACRS Recorts (Open)
P.st p.w.J owfl/ affwwww Discussion of proposed ACRS reports on:
15.1)
Severe Accident Research (MHF/NFD) 15.2)
Draft Regulatory Guide Associated with the License Renewal Rule (MHF/MME) 15.3)
IPE Insights Report (GA/MTM) 15.4)
Health Effects of Low-Levels of Ionizing Radiation (TSK/NFD) 15.5)
Steam Generator Tube Issues (RLS/NFD/BH)
5 1
12:0f 1:00 P.M.
LUNCH hhhhP.M.
Precaration of ACRS Reoorts (Open)
- 16) 12:45 Continue discussion of proposed ACRS reports listed under Item 15.
NOTE:
o Presentation time should not exceed 50 percent of the total thee allocated for a specific item.
The remaining 50 percent of the time is reserved for discussion.
e Number of copies of the presentation materials to be provided to the ACRS - 35.
m
.i
_.. = _ _ - _ -
5
~
12:0 1:00 P.M.
LUNCH
- 16) 12:45 P.M.
Precaration of ACRS Recorts (Open)
]
Continue discussion of proposed ACRS reports listed under Item 15.
NOTE:
e Presentation time should not exceed 50 percent of the total time allocated for a specific item.
The remaining 50 percent of the time is reserved for discussion.
I e
Number of copies of the presentation materials to be provided to the ACRS - 35.
e 2
APPENDIX III:
MEETING ATTENDEES 1
432ND ACRS MEETING j
June 12-14, 1996 i
j NRC STAFF E.
Brummett NMSS i
A.L.
Bryant NRR/EELB H.O.
Christensen NRC/RII
)
M.
Cheok NRR/SPSB I
T.
Collins NRR/DSSA J
S. Dinsmore NRR/SPSB
'J. Donoghue NRR/DSSA/SRXB S.
Flanders NRR/PDLR R.
Frahm NRR/DRCH/HQMB R.
Freudenberger RGN II SRI Catawba T. Fuchigami NRR/SPSB E. Goodwin NRR/OECB R. Jones NRR/DSSA K. Karwoski NRR/DE/EMCB P.T.
Kuo NRR/PDLR A.
Levin NRR/DSSA/SRXB i
B. Martin NRR/DRPE B. Meck RES G. Mencinsky RES/DRA/RDB M. Mitchell RES/DET/EMMCB M. Morgan NRR - Mat'Ls M. Morris RES/PRAB D. O'Neal NRR/DSSA P. O'Reilly AEOD/SPD R.J.
Pratt NRR/PDLR A. Ramsey-Smith RES/PRAB T. Reed NRR/DE/EMCB A. Rubin RES/OSS/AEB P. Shemanski NRR/PDLR L. Soffer EDO J.
Strosnider NRR/DE/EMCB D. Thatcher NRR/EELB J.F. Williams NRR/DRPE ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC P. Abraham Duke M. Barron NUS/LIS S.
Bragg ANS Intern B. Brool:s DOE K.
Caraway Duke Power Co.
A.
Carson Bechtel P. Colainni Duke Power Co.
L.
Connor STS T. Crawford Duke Power Co.
4 Appendix III 2
432nd ACRS Meeting 4
ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC (Con't)
L. Debl Lamb Associates, Inc B.
Duroshul BGE D.
Eggett Com Ed L.
Fairobent Lamb Associates, Inc.
f P.
Fulfons NUS/LIS l
C.
Gallaway NEI j
M. Goldman Health Physis Society / Univ. of California-Davis i
T. Heroux EPRI 4
R. Hunt ANS intern l
P.
Krishna TRW
{
R. Machon TVA BFN W. Mackny Entergy - ANO A. Marion NEI J. Matta Winston & Strawn 1
G.
Peterson Duke Power Co.
4 F.
Polaski PECO Energy G.
Preston TVAN - Browns Ferry M. Quint Embassy of Australia B.
Ricuher DOE T.
Rockwell MPR Associates, Inc.
)
P.
H.
Stockwell DOE K. Sutten Winston & Strawn R. Tedesco Scientech j
H. Trellue ANS Intern M. Tuckerman Duke H. Williams TVAN - Browns Ferry
]
J. Wreathall TWWG 1
A APPENDIX IV:
FUTURE AGENDA The Committee agreed to consider the following during the 433rd ACRS Meeting, August 8-10, 1996:
Sucolemental Safety Evaluation Reports for Evolutionary Plant Desiona - The Committee will hear presentations by and hold discussions with representatives of the NRC staff, General Electric Nuclear Energy (GENE), and ABB-Combustion Engineering (ABB-CE) regarding the proposed changes to the GENE Advanced Boiling Water Reactor (ABWR) and ABB-CE System 80+ evolu-tionary plant designs and the associated NRC staff Safety Evaluation Reports.
Other interested parties will partici-pate, as appropriate.
A portion of this session may be closed to discuss GENE and ABB-CE proprietary information applicable to this matter.
SECY-96-128. " Policy and Kev Technical Issues Pertainino to the Westinchouse AP600 Standardized Passive Reactor Desian" -
The Committee will hear presentations by and hold discussions with representatives of the NRC staff and Westinghouse Electric Corporation regarding SECY-96-128, which includes proposed staff positions on three policy issues concerning Prevention and Mitigation of Severe Accidents, Post-72-Hour Actions, and External Reactor Vessel Cooling, as well as the status of seven key technical issues pertaining to the AP600 passive plant design.
Other interested parties will partici-pate, as appropriate.
A portion of this session may be closed to discuss Westing-house proprietary information applicable to this matter.
Risk-Informed and Performance-Based Reculations and Related Matters - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding several issues raised in the Staff Requirements Memoranda dated May 15 and June 11, 1996, including:
e Role of performance-based regulation in the PRA Implemen-tation Plan e
Plant-specific application of safety goals e
Requirement for risk neutrality versus the allowance for an acceptable increase in risk e
Risk-informed inservice testing and inservice inspection requirements e
Pilot applications for risk-informed and performance-based regulations Representatives of the nuclear industry will participate, as appropriate.
Appendix IV 2
+14th ACRS Meeting Id2Al Risk-Based Analysis of Reactor Ooeratina Experience - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding risk-based analysis of reactor operating experience.
Representatives' of the nuclear industry will participate, as appropriate.
Scent Fuel Pool Coolina Issues - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the staff review of the safety issues associated with spent fuel pool cooling systems.
Represen-tatives of the nuclear industry and other interested persons will participate, as appropriate.
e n-
APPENDIX V LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE
[ Note:
Some documents listed below may have been provided or prepared for Committee use only.
These documents must be reviewed prior to release to the public.]
MEETING HANDOUTS AGENDA DOCUMENTS ITEM NO.
1 Ocenina remarks 0.
Items of Interest 2
Draft Reculatorv Guide, DG-1047, " Standard Format and Content for Aeolications to Renew Nuclear Power Plant Ooeratina Licenses" 1.
NRC Staff /NEI Presentation to the ACRS, Draft Regulatory Guide DG-1047,
" Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," and NEI 95-10, Rev.
O, Industry Guideline for Implementing the Requirements of 1-CFR Part 54 - The License Renewal Rule,"
- NRR, dated June 12, 1996
[Viewgraphs]
2.
NEI 95-10, Rev.
O,
" Industry Guideline for Implementing the Requirements of 1-CFR Part 54 - The License Renewal Rule," presented by Doug Walters, NEI, dated June 12, 1996 [Viewgraphs) 3 IPE Insichts Reoort 3.
Individual Plant Examination Program:
Perspective on Reactor Safety and Plant Performance, presented by Mark Cunningham, Mary Drouin, Allen Camp,
4 Loss of Offsite Power at Catawba, Unit 2 4.
ACRS Presentation, Catawba Unit 2,
Loss of Off-site Power, February 6, 1996, presented by Chris Christensen, Region II, dated June 12, 1996 [Viewgraphs) 5 Future ACRS Activities 5.
Future ACRS Activities - 433rd ACRS Meeting, August 8-10, 1996 [ Handout #5-1]
6 Reoort of the Plannino and Procedures Subcommittee
m
__m e
e Appendix V 2
4t8th ACRS Meeting Al3AN 6.
Final Draft Minutes of Planning and Procedures Subcommittee Meeting - June 11, 1996 [ Handout #6-1]
9 Issues Associated with Steam Generators 7.
Steam Generator Rule Making, June 13, 1996, presented by Jack Strosnider, Chief Materials and Chemical Engineering Branch, Division of Engineering, NRR 8.
Performance-Based Steam Generator Rule, June 13, 1996, presented by Alex Marion, NEI 10 Browns Ferry Nuclear Plant, Unit 3 9.
Tennessee Valley Authority (TVA) Browns Ferry Nuclear Plant (BFN),
June 13,
- 1996, presented by
'the representatives of the licensee TVA 14 Health Effects of Low-Levels of Ionizina Radiation 10.
NRC's Use of the Linear Non-threshold Hypothesis for Health-Effects of Low-Levels of Ionizing Radiation, June 14, 1996, presented by, John E.
Glenn, Chief radiation Protection and Health Effects Branch, Office of Research 11.
Health Effects of Cellular Mutation Repair Response to Radiation:
Low Dose Hormesis and High Dose Carcinogenesis, June 14,
- 1996, preser.ted by Myron Pollycove, Professor Emeritus, Laboratory Medicine and Radiology, University of California, San Francisco 12.
Theodore Rockwell, R6 sums 13.
Graph from Marvin Goldman and Ign V.
Filjushkin " Low-Level Radiation Risks in People" Chinese Medical Journal 107 (8) : 624-26, 1994 14.
E-Mail Memorandum sent by Alan Levin to Noel Dudley, June 14, 1996, Subject, ACRS Presentation by Pollycove 15.
Health Effects of Low Levels of Ionizing Radiation -
432nd ACRS Meeting, June 12, 1996 [ Handout #14-1]
11 Reconciliation of ACRS Comments and Recommendations 16.
Reconciliation of ACRS Comments and Recommendations
[ Handout #11.1]
.o-Appendix V 3
ACRS Meeting MEETING NOTEBOOK CONTENTS
.T.83 DOCUMENTS 2
1.
Table of Contents 2.
Tentative Schedule 3.
Status Report, dated February 9,1995 [ Internal Committee Use Only: Predecisional Material Attached]
4.
Federal Register, 10 CFR Parts 2,
51, and 54. Nuclear Power Plant License Renewal; Revisions, dated May 1,1995 5.
NEI 95-10 (Revision 0),
" Industry Guideline
'for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule", dated March 1, 1996 6.
Letter from T.S.
Kress, Chairman, ACRS, to Ivan Selin, NRC Chairman, dated March 14, 1995: Proposed Amendment to the Nuclear Power Plant License Renewal Rule (10 CFR Part 54) 7.
Draft Regulatory Guide DG-1047 (Supersedes Draft DG-1009): Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses 3
IPE Insichts Reoort 8.
Table of Contents 9.
Tentative Agenda 10.
Project Status Report, dated February 9, 1995 11.
Draft NUREG XXX, Part 1,
Vol.
1,
" Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance (IPE Insights Report) - Distributed previously, attachment not included 12.
SECY-96-051, " Status of IPE and IPEEE Programs," from J.M.
Taylor, EDO, to the Commissioners, dated March 8, 1996 13.
Letter from J.M.
Taylor, EDO, to T.
Kress, Chairman, ACRS, Subj: "Use of Individual Plant Examinations in the Regulatory Process", dated April 10, 1996.
14.
Report from T.
Kress, Chairman, ACRS, to S.
- Jackson,
Appendix V 4
416th ACRS Meeting
&30/)d
- Chairman, NRC, Subj:
"Use of Individual Plant Examinations in the Regulatory Process", dated March 8, 1996 4.
Loss of Offsite Power at Catawba, Unit 2 15.
Table of Contents 16.
Tentative Schedule 17.
Status Report 18.
NRC Inspection Report NOS, 50-413/96-03 and 50-414/96-03, from A.F.
Gibson, Director, Division of Reactor Safety, to Mr. W.R. McCollum, Site Vice-President, Catawba Site, Subj: NRC Inspection Report Nos. 50-413/96-03 and 50-414/96-03 and Notice of Violation, dated March 12, 1996 19.
Catawba Main Power Distribution Operations Training Lesson Plan (for Information Only) 20.
Letter from P. Tam, NRR/PM, Preliminary ASP Analysis, to Mr. W.R. McCollum, Site Vice-President, Catawba Nuclear Station, Subj: Review of Preliminary Accident Sequence Precursor Analysis of Loss of Offsite Power Event at Catawba Unit 2, dated May 22, 1996 9
Issues Associated with Steam Generators 21.
Table of Contents 22.
Tentative Schedule 23.
Status Report, dated June 15, 1996 24.
Letter from Dana Powers, ACRS Member, Subj: Defense in Depth and the Steam Generator Rule, dated June 3, 1996 10 Browns Ferry Unit 3 25.
Table of Contents 26.
Tentative Schedule 27 Status Report, dated June 13, 1996 28.
SECY-95-264 Subj: Restart of the Browns Ferry Nuclear Plant, Unit 3,
f rom J. M. Taylor, EDO, to the Commissioners, dated November 1, 1995
r,
'b.
Appendix V 5
1 4"
41~8th ACRS Meeting i
Q3G%J i
29.
Memorandum from J.R.
Johnson to S.D.
Ebneter, Regional j
Administrator, Subj: Restart of Browns Ferry Unit 3,
dated November 18, 1995 i
14 Health Effects of Low-Levels of Ionizino Radiation i
30.
Table of Contents 31.
Tentative Schedule t
]
32.
Status Report, dated June 14, 1996 33.
Proposed Letter Final Draft 1B of ACNW Report from ACRS/ACNW, to S.
Jackson, NRC Chairman, Subj: Health 4
Effects of Low-Levels of Ionizing Radiation, dated May 17, 1996 34.
Memorandum from Dr. Powers, ACRS, to Roxanne Summers, Technical Secretary, Subj: Health Effects of Low-Levels j
of ionizing Radiation, dated May 18, 1996 4
35.
Memorandum from Dr. Powers, ACRS, to Roxanne S u mm e r s,
Technical Secretary, Subj: Health Effects of Low-Levels of Ionizing Radiation, dated May 5, 1996 36.
Memorandum from Dr.
M.
Steindler,
- ACNW, to Dr.
J.
j Garrick, ACNW, Subj : Health Ef fects Latter, dated May 18, 1996 j
37.
Memorandum from Mr. J. Carroll, ACRS, to Dr. J
- Larkins, ACRS Executive Director, Subj: 3/26/95 ACRS/ACNW Joint Subcommittee Meeting, dated May 18, 1996 i
38.
Draft Work Scope, approved by Mr.
C.
Paperiello, NMSS, Subj: BEIR VII " Scoping Study", dated May 2, 1996 j
39.
Technical Proposal Summary from National Council on 1
Radiation Protection and Measurements, to NRC, Subj:
Assessment of Biological Studies Associated with Health Effects of Low-Levels of Ionizing Radiation, dated February 10, 1995 3
4