ML20217J011
| ML20217J011 | |
| Person / Time | |
|---|---|
| Issue date: | 04/03/1997 |
| From: | Seale R Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-3056, NUDOCS 9708130385 | |
| Download: ML20217J011 (34) | |
Text
.
CdTIFIEDBY DATE ISSUED:
h p
T 4/3/97 R.L. SEAL.E I
L!
6/12/97 J; =sb Iu 06.0 ~88$$
l' eveep/o TABLE OF CONTENTS MINUTES OF THE FOUR HUNDRED FORTIETH ACRS MEETING APRIL 3-4, 1997 Pace I. Chairman /s Report (Open) 1 II. Proposed Regulatory Approach Associated with Stekm Generator Integrity (Open) 2 III. Consequences of Reactor Water Cleanup System Line Break outside Containment (Open) 3 IV. Subcommittee Recort (Open) 4 V.
Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 Requirements (Open) 5 VI. Boiaf, lex Degradation in Spent Fuel Pool Storage Racks (Open) 8 VII. Use of Potassium Iodide After a Severe Accident (Open) 9 VIII. Executive Session (Open) 10 A.
Reports and Memoranda EEPORTS Proposed Regulatorv Guidance Related to Implementa-tion of 10 CFR 50.59 (Ch_a nge s. Tests and Experi-ments)
(Report to Shirley Ann Jackson, Chairman, bl NRC, from R. L. Seale, Chairman, ACRS, dated April 8,
1997)
Risk-Based Regulatory Acceptance Criteria for Plant-Specific Application of Safety Goals (Report to Shirley Ann Jackson, Chairman, NRC, from R.
L.
~~6>jt Seale, Chairman, ACRS, dated April 11, 1997)[ h rt).
1? 11 y.
9700130385 970811 T W SE"3 ff 9
(, m r PDR ACRS J l O,4 Y U S ~ !q.
l UJ 3056 PDR 5
k
((llhlh l h f
IiCIP,N AID ORIG 1NAL.
J mumm M s
\\.
S 4
Operations, NRC, f rom John T.
Larkins, Executive Director, ACRS, dated April 8, 1997) e ProDosed Rulemakino Plan for Amendments to Suboart H and Anoendix A to 1Q CFR Part 20--Resoiratory Protection (Memorandum to L. Joseph Callan, Execu-tive Director for Operations, NRC, from John T.
Larkins, Executive Director, ACRS, dated April 8,
1997) e Proposed Rulemakina Plan for Emeroency Plannino Recuirements for Permanent 1v Shutdown Nuclear Power Plant Sites (Memorandum to L. Joseph Callan, Execu-tive Director for Operations, NRC, from John T.
Larkins, Executive Director, ACRS, dated April 11, 1997)
B.
Reconciliation of ACRS Comments and Recommen-dations C.
Report on the Meeting of the Planning and Proce-dures Subcommittee Held on April 2, 1997 (Open)
D.
Future Meeting Agenda S.
li f~
t 4
APPENDICES I.
Federal Register Notice II. Meeting Schedule and Outline III. Attendees IV. Futuro Agenda and Subcommittee Activities V. List of Documents Provided to the Committee
i.
o MINUTES OF THE FOUR.HUNDRED FOURTIETH MEETING OF THE
=
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
-APRIL 3-4, 1997 i
ROCKVILLE, MARYLAND The 440th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on April 3 - 4,. 1 9 9 7.-
The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached-agenda.
The meeting - was open to public attendance. There was one written statement and three requests for time to make oral statements regarding issues on the agenda.
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 l
1 are available for rtrchase from Neal R. Gross and Co.,
Inc., 1323 Rhode Island Avenue N.W., Washington, D.C.
20005.)
ATTENDEES ACRS Members:
Dr. Robert L. Seale (Chairman), Dr. Dana A.
Powers (Vice-Chairman),
Dr. George Apostolakis, Mr. John Barton, Dr.
Thomas S. Kress, and Dr. William J. Shack.
Drs. Mario Fontana and Don Miller were absent for the entire meeting.
Dr.
George Apostolakis was absent for a portion of the morning on April 3,
1997.
(For a list of other attendees, see Appendix III.)
I.
CHAIRMAN'S REPORT (Open)
(Note:
Dr.
John T.
Larkins was the Designated Federal l
Official for this portion of the meeting.)
Dr. Robert L. Seale, Chairman, ACRS, convened the meeting at 8:30 a.m.
and reviewed the schedule for the meeting.
He announced that the Committee would discuss the appointment of new members during this meeting; that Members were invited to meet on Friday, April 4, 1997, with Mr. John Szabo, Office of the General Counsel, to discuss conflict-of-interest issues; and that Members should notify the NRC staff if they were interested in attending an NRC meeting on severe accident research on May 5-8, 1997.
Dr. Seale also drew attention to the Items of Interest document, and in particular to an NRC Press Release on violations at the Beaver Valley Nuclear Plant and to a letter dated March 12, 1997, from David L. Morrison, Director, Office-of Nuclear Reactor Research, to Dr. Thomas Boulette, Chairman, Nuclear Safety Research Review Committee.
t 4
440th ACRS Meeting 2
April 3-4, 1997 II.
Prooosed Reaulatory Acoroach Associated with Steam Generator Intecrity (Open)
[ Note:
Mr. N. Dudley was the Designated Federal Officjal for this portion of the meeting.)
Introduction Dr.
- Seale, Acting Chairman of the Joint Subcommittee on Materials & Metallurgy and severe Accidents, noted that steam generator tube integrity is a difficult technical and regula-tory issue.
He stated that because of the Committee's continuing interest in steam generator tube integrity issues, the staff was asked to report on the status of these matters and on the associated draft memorandum to the Commission.
Staff Presentation Mr. Jack Strosnider, Office of Nuclear Reactor Regulation (NRR),
discussed the background of the steam generator integrity rulemaking and the role of the associated regulatory guide.
He presented the following preliminary conclusions from the draft risk assessment and the draft regulatory analysis:
Risk from steam generator tube ruptures induced by severe accidents could increase for some alternate repair criteria.
Severe accident risk does not warrant plant backfits to reduce risk.
e Licensees will need to assess severe accident risk as part of any relaxation of current criteria, o
The staf f is reconsidering whether rulemaking is the best vehicle for revising the steam generator tube integrity requirements.
Mr. Strosnider stated that one alternative to rulemaking would be to implement some changes via the current regulatory framework using compliance backfit as the basis.
The changes would modify the technical specifications to require opera-tional assessments and condition monitoring programs.
In addition, assessment of severe accident risk associated with alternate repair criteria would follow guidance provided in a regulatory guide prepared in accordance with draf t Regulatory Guide DG-1061, " Approach for PRA in Risk-Informed Decisions on Plant-Specific Changes to Current Licensing Basis."
Both the
4.
440th ACRS Meeting 3
April 3-4, 1997 compliance backfit and risk assessment requirements could be imposed through generic letters.
Mr.
Strosnider explained that the staff was preparing a memorandum to the Commission that would present alternatives to rulemaking.
The Committee and the staf f discussed techni-cal aspects of the proposed approach, such as the 40 percent through-wall acceptance
- criteria, sizing tube
- defects, measurement of crack growth rate, and degradation mechanisms.
Industry Presentation Ms. Sherry Bernhof t, Wisconsin Public Service, agreed with the staff that it is appropriate to look at end-of-cycle condi-tions.
She stated that the proposed regulatory guide includes an appropriate way to do condition monitoring.
Conclusion This briefing was for information only.
The Committee expressed an interest in reviewing and commenting on the memorandum to the Commission.
III. Consecuences of Reactor Water Cleanuo System Line Break Outside Containment (Open)
(Note:
Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.)
Mr. Barton, Chairman of the Subcommittee on Improved Light Water Reactors, stated that, during the review of the advanced boiling water reactor design, the ACRS identified safety-related deficiencies in the reactor water cleanup (RWCU) system.
The ACRS requested the NRC staff to perform a study to investigate the consequences of an unisolated RWCU pipe break outside primary containment for operating boiling water reactors.
Mr. Ronald M.
Young, Plant Systems Branch, NRR, stated that NRR has received agreement from three boiling water reactor plants to participate voluntarily in the RWCU study.
The study included a simulated RWCU pipe break using the RELAP-5/ MOD 3 Code.
The contpinment environmental conditions were determined using the CONTAIN code.
The staff conducted both in-house and external database searches.
The study addressed several key issues such as reactor core coverage and cooling, and the secondary containment environment.
The study also included recent related events for boiling water reactors.
4 :,
e b
440th ACRS Meeting 4
April 3-4,-1997 This briefing reported only on the status of.the study.
The staff has completed its final report on this issue; however, the report is currently under_ review by NRC management.
The Committee plans to review the proposed final report of this study after it has been completed by the staff.
Conclusion This briefing only-covered the status of the report of the study, without detailed discussion of the technical descrip-tion and the results of the study.
The Committee plans to review the proposed final report at a future ACRS meeting.
IV.
S.ghcommittee Reoort (Open)
(Note: Mr. P. Boehnert was the Designated Federal Of ficial for this portion of the meeting.)
Dr.
T.
Kress, Chairman of the Thermal-Hydraulic Phenomena subcommittee, provided a report on the results of the Sub-committee's March 28, 1997 meeting.
The Subcommittee met to review the methodology proposed by the Westinghouse Electric Corporation for the modeling of the AP600 long-term cooling (LTC)- accident
- analysis, using its COBRA / TRAC - code.
In particular, Westinghouse was interested in obtaining the Subcommittee's initial reaction to the viability of its so-called window approach used in the LTC methodology.
Dr, Kress noted that the question posed by the Subcommittee at this meeting. was, "Is the window approach acceptable for modeling of the LTC scenario?"
The Subcommittee concluded that this approach is viable.
However, some issues require additional work by Westinghouse.
In particular, since Westinghouse has to couple the COBRA / TRAC code with its containment code (GOTHIC) for the LTC analysis, questions remain regarding the conservatism assumed in the COBRA / TRAC calculations and the associated uncertainties.
t The Subcommittee expressed concern regarding the approach selected by Westinghouse to address this matter; i.e.,
use of a complex code not suitable for the specific modeling problem at hand (i.e., quasi-steady-state conditions).
The Committee extensively discussed this issue.
Dr. Powers suggested that the Committee pursue, with the NRC Office of Nuclear Regulato-ry Research, the issue of the development of analytical tools that will be appropriate to the specific problem at hand.
e 4
440th ACRS Meeting 5
April 3-4, 1997 Conclusion The Thermal-Hydraulic Phenomena Subcommittee plans to continue its discussion of this matter af ter Westinghouse has completed additional work.
V.
Proposed Reculatorv Guidance Related to Imolementation of 10 CFR 50.59 Reauirements (Open)
[ Note: Mr. M. Markley was the Designated Federal Official for this portion of the meeting.)
Mr.
John Barton, Chairman of the Subcommittee on Plant Operations, introduced the topic to the Committee.
He noted
- that, in October
- 1995, Chairman Jackson raised several questions regarding the process for implementing the provi-sions of 10 CFR 50.59, " Changes, Tests and Experiments."
He stated that the chairman had requested the NRC staff to perform a systematic reconsideration and reevaluation of the process due, in part, to the problema experienced at the Milletone Nuclear Power Station.
He noted that the staff had created an action plan to examine the existing guidance and to recommend positions on the regulatory issues.
Mr. Barton stated that the Commission was briefed on March 10, 1997, on the proposed regulatory procece improvements as dascribed in SECY-97-035. He introduceo Mr. Tim Martin, Director, Division of Reactor Programs Management, NRR.
NRC Staff Presentation Mr. Martin introduced Mr. Loren Plisco, Branch Chief, Special Projects Office for Millstone, and Ms. Eileen McKenna, Senior Ret: tor Engineer, Generic Issues and Environmental Projects
- Branch, NRR, who led the discussion for the NRC staff.
Significant points made during the discussion included:
e 10 CFR 50.59 permits licensees to make changes without NRC approval, o
Problems at Millstone fell into three basic areas:
Failure to prepare written safety evaluations for changes to the facility as described in the Final Safety Analysis Report (FSAR).
Physical changes were made to the facility without performing 10 CFR 50.59 evaluations.
e a
440th ACRS Meeting 6
April 3-4, 1997 l
The FSAR has been incorrect for some items since original construction / installation.
These errors existed, in part, due to documentation being locat-ed in other licensing and regulatory commitments.
These were considered "de facto changes."
J e
At Millstone, the majority of 10 CFR 50.59 safety evaluations for modifications were done well.
- However, most problems were noted in safety evaluations for maintenance, procedure
- changes, and emergent design issues.
Also, the FSAR was not viewed nor maintained as a design-basis document.
o Concerns about the 10 CFR 50.59 process include:
the scope of 10 CFR 50.59 is limited to the facili-ty or procedures described in the FSAR, ambiguity exists over what represents an unreviewed safety question (USQ), and applicability is unclear for existing conditions, o
The Executive Director for Operations (EDO) established an action plan to examine the existing guidance and to recommend positions on the regulatory issues such as:
application of 10 CFR 50.59 to the resolution of degraded and nonconforming conditions, definition of reduced margin of safety as defined in the basis of any Technical Specification, increase in probability or consequences, and deleting information from safety analysis reports.
e The action plan addresses policy issues and suggests options for possible rulemaking regarding the sufficiency of the scope of 10 CFR 50.59 and possible thresholds for USQs.
Industry Presentation Mr. Tony Pietrangelo of the Nuclear Energy Institute (NEI) provided a brief discussion of the proposed guidance provided in SECY-97-035.
He also discussed NSAC-125, " Guidelines for 10 CFR 50.59 Safety Evaluationr," issued June 1989.
He noted that the staff had not endorsed this industrial standard, in part due to its allowance for some increases in risk.
He
440th ACRS Meeting 7
April 3-4, 1997 added that NEI has attempted to improve on NSAC-125 through development of draft guideline NEI 96-07, Revision A, " Guide-lines for 10 CFR 50.59 Safety Evaluations," issued June 1996.
Significant points made during the discussion includes e
The positions in SECY-97-035 are a departure from how NSAC-125 has been implemented over the years.
There is no easy way to address potential changes in 10 CFR 50.59.
e The short-term plan is to get the appropriate guidance from NSAC-125 into NEI 96-07. However, rulemaking may be inevitable for long-term solutions to the policy issues, e
There is a need to better define safety margins and to establish thresholds for increases in probability and consequences.
The use of the term "any" is very restric-tive and would likely cause diversion of resources from more risk significant activities.
Dr. Apostolakis questioned the extent to which the issues at Millstone were unique relative to other plants.
The staff stated that the safety evaluations completed at Millstone were not addressing some important issues and that the staff was accepting degraded conditions through longstanding compensato-ry measures.
The staff stated that most safety evaluations were done well but acknowledged that there were some problem areas (e.g., maintenance).
Dr. Powers questioned the consideration of uncertainty.
The staff stated that uncertainty is not quantified for most 10 CFR 50.59 reviews, adding that this makes the importance of knowing the safety margin more important.
The staff stated that the margin of safety is usually related to the bases of the Technical Specifications.
Dr. Powers questioned the specificity of the language in SECY-97-035.
He expressed the view that it may inhibit the use of judgment to consider what is reasonable assurance.
Dr. Kress questioned the allowance for increases in risk.
Industry representatives stated that 10 CFR 50.59 does not really provide for increases in risk, increases in probabili-ty, or consequences. NEI representatives stated that this may be a major reason to consider rulemaking.
At the conclusion of the briefing, the ACRS decided to prepare a report to the Commission regarding this matter.
~
A 440th ACRS Meeting 8
April 3-4, 1997 Conclusion The Committee issued a report to Chairman Jackson, dated April 8,
1997, on this matter.
VI.
Boraflex Deoradation in Spent Fuel Pool Storace Racks (Open)
[ Notes' Mr. N. Dudley was the Designated Federal Official for this portion of the meeting.)
Introduction Dr. Thomas S.
Kress, Chairman of the Onsite Fuel Storage and Decommissioning Subcommittee, introduced the presentation by stating the acceptance criteria for margins to criticality in the spent fuel pools.
He explained how boraflex is used to meet the required margin and identified the potential problems associated with boraflex degradation.
Af ter noting the NRC information notices and generic letter associated with boraflex degradation, Dr. Kress called on the staff to begin its presentation.
NRC Presentation Mr. Laurence Kopp, NRR, expiuined the evolution of spent fuel pool rack designs and the importance of neutron absorbers. He presented the effects of boraflex shrinkage caused by gamma radiation and of the gradual release of boron carbide caused by long-term exposure to spent fuel pool water.
Mr. Kopp addressed the factors affecting boraflex dissolution, the regulatory requirements for criticality prevention, and the corrective actions that could be taken by licensees.
Mr. Kopp described the information requested by Generic Letter 96-04, "Boraflex Degradation in Spent Fuel Pool Storage Racks," and the staff activities planned as a result of the licensee responses.
He completed his presentation by identifying industry and Electric Power Research Institute (EPRI) efforts to measure and address boraflex degradation over the long term.
The Committee and Mr. Kopp discussed the following:
e the advantage of _boraflex compared to other neutron absorbing materials, the physical changes to boraflex resulting from absorbing e
neutron absorption, e
plans for conducting a probabilistic risk analysis,
-. - ~... -.
- r
&y 440th ACRS. Meeting 9
April 3-4,J1997 ~
I e
suberiticality criteria for unborated and borated spent
. fuel pool water, solubility-of boron lost from boraflex, i
e replacing existing fuel storage racks, and
'e availability of the results of expn iments conducted at
- foreign laboratories on the burnup vf neutron absorbers.
'Dr.
Kress stated that the Committee may want - to hear. a presentation on the Westinghouse code used to. calculate-the suberiticality of the fue.1 in the spent fuel pool.
conclusion This briefing was for information only.
No Committee action was required.
1
- VII. Use of Potassium Iodide Af ter a Severe Accident -(Open)
(Note: Mr. A. Singh was the Designated Federal Official for this portion of the ineating.)
Introduction Dr. Robert L. Seale, Chairman of the Occupational & Environ-mental Protection Systems Subcommittee, stated that the purpose of this session - was to hear a briefing by repre-sentatives of the NRC staff, NEI, and the State of Illinois concerning the staff's position on a petition for rulemaking filed by a private citizen to reevaluate the policy regarding the use of-potassium iodide-(KI) after a severe accident at a nuclear power plant.
NRC Staff Presentation The staff briefed the-Committee on - the proposed Commission paper which provides a resolution to the. petition.for rule-making._
The petitioner requested that the Commission amend its regulations 10 - CFR 50. 47 (b) (10) to' specify that the prophylactic use of KI for the general population within the plume exposure pathway _ Emergency Planning Zone (EPZ) for each licensed nuclear power reactor be identified as one of the
~
" range of protective actions" required to be set forth in State and local EmergencyLPlans.
In 1996, the Federal Radiological Preparedness Coordinating
. Committee 'convaned an ad hoc Subcommittee to review new
4.
g y
44oth^ACRS: Meeting:
10 April 3-4, 1997-r information~ and - comments - on this matter 'from - interested
- parties.
The Subcommittee stated that without changing the
- Federal-policy, and interceding in the-State's.perogative to-make its own decision on whether or not to use KI, the Federal Government-' (NRC, or - through. FEMA, etc. )
should fund ' the -
i purchase - of a = KI. stockpile for any State' that,. hereaf ter,
- decides to incorporate-its use as a protective measure for-the-i
- general.public.
However, ituis the staff's position ~that a-revision to the regulations is unwarranted -because the approach of. stockpiling XI and advising States of the avail-ability of the stockpile subscantially addresses the fundamen-
~
tal concerns behind the petition, without the burden associat-
. ed with requiring changes -in all State and -local Emergency Plans.
The staff believes-that given.these circumstances, unlike those which existed at the time of the Three Mile Island accident, KI could be made available if needed in the i-future.
As a result, the staff recommends that the petition' for rulemaking be denied.
Representatives of-NEI and the State of Illinois concurred 4
with-the staff recommendation that.the petition be denied and that States and localities be allowed to decide when to-L include KI in their Emergency Plans for general public-use.
The staf f concluded that the stockpiling or predistribution of n
KI-for the general public will not add any significant health and safety benefit to the adequate level of protection currently provided by existing emergency preparedness at and around commercial nuclear power plants.
h conclusion e
The Committee plans to discuss a proposed report on this matter during its May 1-3,-1997, meeting.
-VIII'..
EXECUTIVE SESSION (Open)
(Note:
Dr.
John-T.
Larkins was. the Designated Federal Official for-this portion of the meeting.)-
A.
- Reports and Memoranda-REPORTS O
Procosed Reculatorv Guidance Related to Imolementa-
. tion-of 10 CFR-50.59 (Chances. Tests and Exneri-
.ments)
(Report to : Shirley Ann Jackson, - Chairman, 4
NRC, from R. L.-Seale,-Chairman, ACRS,' dated April 8,.1997) 4 4
4 n,-..
-~,
r e
=-,c,--
,we
-,, ~, - -, -,,., -
,.,,.wa.
...--.w,n..
v--
a 440th ACRS Meeting 11 April 3-4, 1997 Risk-Based Reculatory Acceotance Criteria for Plant-Soecific Acolication of Safety Goals (Report to Shirley Ann Jackson, Chairman, NRC, from R. L.
Seale, Chairman, ACRS, dated April 11, 1997)
Establishina a Benchmark on Risk durina Low-Power and shutdown Ooerations (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated April 18, 1997)
MEMORANDA Pronosed Rule - Financial Assurance Recuirements for Decommissionina Nuclear Power Reactors The Committee decided not to review the proposed rule.
(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T.
Larkins, Execu-tive Director, ACRS, dated April 8, 1997).
Procosed Rulemakino Plan for Amendments to Subcart H and Aopendix A to 10 CFR Part 20--Resoiratory Protection The Committee decided not to review the proposed rulemaking plan. (Memorandum to L. Joseph
- Callan, Executive Director for Operations,
- NRC, from John T.
Larkins, Executive Director, ACRS, dated April 8, 1997.)
Procosed Rulemakino Plan for Emeroency Plannino Recuirements for Permanently Shutdown Nuclear Power Plant Sites The Committee decided not to review the proposed rulemaking plan.
(Memorandum to L.
Joseph Callan, Executive Director for Operations,
- NRC, from John T.
- Larkins, Executive Director, ACRS, dated April 11, 1997)
B.
Reconciliation of ACRS Comments and Recommendations (Note:
Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.)
The Committee discussed the response from the EDO to ACRS comments and recommendations included in recent ACRS reports:
EDO letter dated March 31, 1997, responding to the ACRS report dated March 19, 1997, concerning the NRC Of fice of Nuclear Regulatory Research Program to Demonstrate the Adequacy of the RELAPS/ MOD 3 Code to Analyze AP600 Passive Plant Behavior, o
e 440th ACRS Meeting 12 April 3-4, 1997 The Committee decided that it was satisfied with the EDO response on this matter.
C.
Report on the Meeting of the Planning and Procedures Subcommittee (Open)
The Committee heard a report from Dr. Seale on the Plan-ning and Procedures Subcommittee meeting held on April 2, 1997.
The following items were discussed:
1)
DOCUMENTS REFERRED TO IN ACRS REPORTS / LETTERS Certain documents were referred to in the report to Chairman Jackson approved by the full Committce on the Human Performance Program Plan.
While the Subcommittee Chairman was familiar with all the documents cited in the text of the report or the list of references, many of the documents had not been distributed to ACRS Members, nor to the staff.
Members were reminded to distribute supporting documents well in advance so all Members would "have benefit of the documents referenced" before reports or letters are approved.
(Carried over from March 5, 1997.)
RECOMMENDATION The Subcommittee recommended that the cognizant Subcommittee Chairman and Staff Engineer ensure that all documents to be referenced in an ACRS report or letter are distributed to all ACRS mem-bers prior to the meeting at which such a report or letter is written.
A further check will be made during the final review of the draft report or letter prior to presenting it for final approval.
2)
PROMINENT ISSUES FOR THE REMAINDER OF FY 1997 Dr. Scale has prepared a list of prominent ACRS issues for the remainder of CY 1997, which he will discuss at the Atomic Safety and Licensing Board Panel Meeting later this month.
If the Committee agrees that the list represents the Committee's priorities for the next several months, the list can be used to prioritize Subcommittee meetings and can be made available to the NRC Chairman.
. -. _. ~. -.
. -. - ~ _.
1-
[440thACRSMeeting 13 AprilL3-4, 1997 RECOMMENDATION The Subcommittee recommended that this list be reviewed and approved af ter any suggested Member changes have been made.
3)
ACRS WORKLOAD A report on-anticipated subcommittee meetings and matters to be considered during the full Committee meetings was presented.
The planned ACRS activi-ties are substantial and as a result, it is sug-gested that the Committee prioritize issues for
-Subcommittee meetings.
RECOMMENDATION The Subcommittee recommended that the staff indi-cate the potential workload for Members and provide this report to the committee for prioritization of Subcommittee meetings.
4)
EVALUATION OF TIME SPENT DURING FULL COMMITTEE MEETINGS IN CY 1991 An evaluation of time spent by the Cc nittee during the full Committee meetings in CY 1996 was present-ed.
The results of the evaluation indicate that the total time spent in preparing reports / letters during 10 meetings held in CY 1996 was about 48% of the total meeting time.
RECOMMENDATION The Subcommittee recommended that the staf f contin-ue to track how the Committee utilizes its time and provide a quarterly report to the subcommittee-to determine possible improvements in the use of Committee time.
5)-
APPOINTMENT OF MEMBERS
-Recommendations of the ACRS and the Screening Panel were sent to the-Commission on March 19 and 21, 1997..The Commission has been requested to make a decision =by April 11, 1997.
.l,,
n-.
c
y l1;
. A i
1440th-ACRS; Meeting:-
14 f
April 3-4,L1997; 6)=
NEW BUDGET PROCESS FOR FY 1999 The Commission has instituted a new budget process, starting with the FY 1999 budget.
Each office is being asked to determine the funds needed-to imple-ment each of the' strategic initiatives.
Funds for these strategic initiatives must come from cuts in other areas, i
4 7)
- INTERNATIONAL ACTIVITIES e-A fax message was received from Dr. Birkhofer, RSK, on March 11, 1997, stating that he would be available in late October for the Quadri-partite Meeting.
A fax message was sent on March 24,
- 1997, to Dr. - Togo, Science and Technology Agency,. requesting' -information concerning the Quadripartite Meeting.
A reply to this fax was received from Mr. Asakawa stating that the Japanese cannot have the meeting in October and prefer the date of January 12-16 or 19-23, 1998.
EECRMMENDATION
~
The Subcommittee recommended that the Members determine the preferable January 1998 date and coordinate with Dr. Birkhofer, Chairman of the German RSK Committee, on April 30,
- 1997, before communicating their choice of dates to the Japanese, e
Discussions are continuing with RSK on the joint ACRS/RSK meeting on April 30, 1997.
ACRS Members will be assigned agenda topics to discuss.
The proposed final agenda was--dis-cussed.-
RECOMMENDATION The Subcommittee recommended that Members review the agenda, including their assigned topics,: and approve a. final-agenda.
The Committee suggested adding probabilistic risk
. assessment and digital instrumentation and 1
control.cystems under " Miscellaneous."
9 F
T f
___y y._
.--___,w.
.c..
- .n~.
sg u
4-q b
1440th ACRS. Meeting 15 April 13-4, 19971 8).
NUCLEAR SAFETY RESEARCH REVIEW COMMITTEE A. report by the Nuclear Safety-Research _ Review Committee, dated January-15, 1997,:was_ discussed.
A letter dated. March: 12, 1997, from.Dr. David - L. -
Morrison,- Director, Office of Nuclear Reactor Research, to Dr. Thomas Boulette, Chairman of the Nuclear. Safety Research Review Committee, and a Memorandum to the Commission from L. Joseph callan,
- EDO, dated March -13,
- 1997, also addressed the subject of ACRS/NSRRC coordination.
Some response to these documents might be advisable.
RECOMMENDATION The Subcommittee recommended that Members discuss these documents and the appropriate response.
The Committee decided not to prepare a response.
9)
MEMBERS' ISSUES s
A memorandum from Dr.
Powers recorded his observations of the revised procedures for letter-writing during the March ACRS meeting.
RECOMMENDATION s
The Subcommittee recommended that Members read and comment on Dr.
Powers' memorandum and provide additional comments on how the new procedures are working, as appropriate.
A memorandum from Dr. Powers recommended that ACRS-review the nonconservative operations during isolation of a reactor recirculation pump seal leak at the Clinton Power Station.
RECOMMENDATION The Subcommittee recommended that Dr. Powers,
-Dr. Apostolakis, and Mr. Barton develop a way of tracking those events that involve human 4
and organizational performance issues for
-future review.-
t
-e A memorandum - from Dr. Powers identified re-search-topics and recommended that time be set aside at a future meeting _ to discuss ' ' this matter.
4a
?
u.,.,,,
~
m
-m--
41--
-~
.~
.. ~ -. -
~.
~
440th ACRS' Meeting 16
-April 3-4, 1997 o
REtOMMENDATION-The Subcommittee recommended that-the Commit-tee continue to collect topics to be reviewed with - the Director of-the Office of Nuclear Regulatory Research.
10)
TRAVEL e
Requests were received from Drs. Kress and Fontana to attend the American Nuclear Society _
meeting in Orlando, FL on June 1-4,
- 1997, e
A request was received from Dr. Miller to attend one day of a workshop on Nuclear Utili-ties Software in Bloomington, IL on May 7,
1997.
e A request-was received from Dr. Apostolakis to attend a meeting.with senior Institute of Nuclear Power Operations management on proba-bilistic risk assessment in Atlanta, GA on April 14-15, 1997.
RECOMMENDATION The Subcommittee recommended that all four requests for travel be. approved.
The Committee approved all four travel requests.
D.
Future Meetino Acenda Appendix _ IV summarizes -the proposed items endorsed by the Committee for the 441st ACRS Meeting, May 1-3, 1997.
The 440th ACKS meeting was_ adjourned at 7:10 p.m. on Friday,-April 4, 1997, i
i
Federal BaWater / Vol 82. No. 54 / Thuredey, ndarch 30, 1997 / Notices ess enhorsted water was ecoesplashed someulted with Preak Nisiolek of the aspresentassves of the nedser todustry the aos of BaseSou, e asutrea Blinois t of Nuclear safety,.
will panicipmes, e appropriana.
i
. However, meent tants have sugarding envie=====a t tapact er s*80 AX-J888 AX "-
- e/
tion samments.
N e
ar.d :':2' "";er ca as. e<-
-t
= s,,, T 'j"f,,e:: = f y la the spesi nelpoolInom than assed spaa the eenhumamatal
,,,,,,,w j
suScleat to enewe that the k.sr is assessument, the Connaission sencludes of senator weest alenamp systaus e
i smalataland below S.06.
that the psopened acalon will act have euesMe-e sigalScant eSuct on the qualig of the Repsummamelves of the meniser ladustry I
hymeer e(the PNposed bassen savtreament..* -
y,the wel partisspues,as appsp A88888 Commanisdom has deternhead met pg iIde AK-f f Jef AX: ="'"-*
l The n--A laa had completed ite
- psoperv en entisemassatalimpact 88 pert (OpenFThe Commdass wul hear e e
evaluation of the proposed action and
=ama====* Gor the action.
upon me h et the Thumal.
i concludes that the licensee's pooposal to For farther with sospect to the d o,o.ed acd.-as nasa. F ACRS on, any alternatives with equal or Sahguards will hold a meeting en Apru Chairman wul make numerks r
srester environmentalimpact need not 35-5,1997,la Conference Room T-253, ' suganung sendes of mesdag.
be evaluated. As na alternative to the 11645 Rockville Pike, Rockville, s.ss A.as.soso AX:annWIss anyedaalan pro action, the staf considered Marylar.d. The date of this naasting was k spent peeraset semesup mods (Openh i
of the proposed action. Denial of Published in the Federal The=== wul hear pe===wa== by r
the applicatica would result la no onThwedey,}emanry23,tegy sad hoW assumiam wth armenom et change la suust enviromansatal (s2 FR 3539).
NRC the of impacts. The environmentalirpts of Thusaday, Asse a, tesy surmann used la synt heel peel saareas susks the propoemi acties and the ahuantiver eae Am. Am.
m.,,,e, ny sad umes nopenses = cemente inns,es.
i.
action are almilar, she Acts theiruuan topomb Acts es,"BaraSea Dayudessen is $past Fuel ajan,,,etvirusegaminiurine*
N ir=an wul enho numarks susage amts.-
sesenties aondem et meetiasand mapsummenhos of the anelserindesary This action does not lavolve the see esmass briety segudlag items et surrent wul penidpees, as appmeprises.
of any resounse t'otc _ My toesrest.
thh assaism. the -m sods AX-2 m AX:Use ofMaassaism e
4 considered in the Final Enviremensamt wul discuss kr peepuesten et hdide After e seven Assident (OpsabThe f
Statonnent for the Byron Station, Units 1 Acts myrm.
Cumnian wul har premannes by ad and 3 and Breldwomt 8mden Unit 1 ares AX-em AX:stupenedasysisessy held disasemiens with the
'"ous of and3' Appread A weh aimm toNRCmat % & &.peHey em l
AussyWy (OpenbThe Casantass wiu haar the use of poemasissa todida aAer e seeme I
Agencies andPersons Consulted P'esessmalens by and bow discussians with accident and other reissed issues.
I nonssamu m etseratCeenu se sas rX-sa rx:rusm Acts la accordance with its stated policy, segulassry ter '
6 Asafesties (OpenbThe Commattens win on February it.1997,the ster samaansensener lesass.
discuss the t----"d-of the Fhmaing
.,p l
I t
resersi Eagleter i Vol. W. No. 641 Thursday, b4 arch 20,1997 / Noticos 18405 4 Presedwee i*-
--'une is sesedeman wish ! ' - N te(d) P.t.
la b larm of an affidevit. tr.
t.
O PMPesed ter esseWaret6ee MI e6-443. 8 beve desesnteed shed h 6 p-ary lawyws, a tertincab of wivits.
.wmi'im hature enestWs.
O dose pertions of skis notede&wre f ee8 P&7ase &Freparean.e AOLS esta abould state the nature wgg pg %
g,,disones anuare thes mieu ao 1 es the et the arri o,e inte'est, the reason for the es
,,g g,g
,g gg, hue ' ' of ACR8 Adeteery Ceemedese per s UAC taab(cXII.
'"98888. ""d O' A*'"" '88t"I'd*
/eteseseemereessel ikk eneettaas, so wou ne proposed esparte end to daeases homennessa ets edsene g Poseases eney ruguest notincation of e,
- '*dd"*d Pre *us emensas se wak.h wedd seest. top e dearly hearing by wrtting to the SEC's omwenenned leventes of pereenal petvecy per Seastary.
leewee sud as ok eyerouses Hek ed g u1C S&3Mth8)-
ALatteess: Secretary, SEC. 450 Fihb I
P8sths'l*88*euse namedies to be 8s8"edey, Apre 8. tory
' e newed.whederto been Street, N.W., Washlagton, D.C 20549.
Apphcant.1HS Avenue of the 8JO A&#N AMiy ofIAe eenmuodwneobedmind b
'e Americes.New York, New York 10105.
ash time
-[Q 8 ied 'P0ft PWerfHaft DePCseuttost 000ff ACTl esal dIb Phadpd Prudwn seehestentmed sentmatleg Mr.
Elaine bl 80g8. Senior Counsel, et ni m,n,,,,g ag a gg Sea Dwslewoey,Ght, n==we (302) M3-OS F2 (Division of investment
^u treetA (telepheme 3o1/416-r8641, between osedue d ACR3 bushme u 3 --
m and poseemani emetters rdettag to the ACF.57 M and tilM RIT.
_ rt,OlBce oflavestment
^
- *' *1b
_.. Opospany Regulation),
deemed w mad ter part se SUPPI,austW M N M N
,,,,,,,,g,,,la,,,(u,s,e,Wh
,edwe,w.ee,,s,e new u
m C wumm,.-
sonowa i.. e-ofthe Duect Deal Aeuses number to FedWorld la application. De com to appucation ye,,
,,g,g.,,,4 o Mdesse 1400) 30Hs73 Coonemleems and la wu, we.w e so,. tion the de-me-ow er Ap.e.sdworld. Thew kJ obtained for e fee from the SEC's e de.,t me. e ae - aeo naar.oo n,-ci.
upwanmesed lernesse of peesenal petvecyfl
- vouahne tar ehrwdendin
- I*****' *' W'""g er m*wtag on wm
_*~
8>N A & llte0P.Mt,% ' ' = =fAOt3
'W'
~ '. A Asperte(Dree4The Coen=tew wiu
^*3^#W'e li 1
PP cant is e closed end memumm he discunsame of pro ACRS Dohad: bess tr.toer, sea.iagemeest inves es organteed as e,tment company that sepute se seamers eene64wed thAs Andrew 1. ma6=
tion under b 88"#84 ee **U es P'*Pamd reports AMeery Ceaustesse & - M Officer.
news of Maryland, A cant registered
,"g %
"*8',g'j g IFR Dec. BMD64 Filed blt>-47 648 eenl tader the Act and a registretion f
- d 4
p men le causse sees pen,
r w 3.w M as,ee,y e pgeasday statement on Form N-2 on Novembar 33 g
17.1969. Applicant's tretion IOpeakThe r iiise wiu es.ttege tu statesment wee declare Nective on a*.
asestos oflessne of algalacant hopcetnac* SECUPUTIES A800 EXCDMP$f!E January 19,1990, and op Ucant
%.acluding e hneehains of the alesee activitsee lot FT 1eer.
gogggggggpg n==namarv=A e lic 05 ofits CrP & f480P M Mescalieneme cosevisest Cosiperuy Ast flatemos Pte-abares shortly er.
to the conducs of Comminen malvtues
- til-teer)
- 2. On December 7,1994, e phcanCs The CneumJttee wtU discuss morters hoard of directors comelde and messere and oped&c leeuse that wars not ACtf hierieged teul644erhet Trust, tric.;
Ped e We of hM eD of esopleend duttas provtous smeettmos, es thee tietseof AppliseWon usets and liabilities of op cant to
)
and ets11eMb of taAwneettoe ts.
the A111 ann ti Market Stret Proc.dwee the esaduct and beerch 14. toer.
Trust.1r
. Acquiring Fund. N "pertaciguea la ACRS moeunes wwe
. AemeCf3 Securttles med Emhange bo d L 49etare seeds the fladings
. _ to the Federal Regleter as Ochbw Commision ("$EC").
pequired try rule 17e 8 under the Act.
l
,,",,,n,,
ACTIcet: NatioS of application for en 14 that the rearpanisation was in b a
eney be ud t y e.=ed ore of tin pubuc. order und the 1svestiment Company best interest of a beant and that ther, reaerdlag wiu
)
daintag the opee par,tions of ined saly Act of IMO (h "Act").
wondd k n o dil on, virtue of the meeting. and i
-ans aney be sehed sedy b cachange,in value of communee, sie esswuhmou,y annenhas of APrucastri ACM Mameyed Multi Mattat held et that tine by applicant's I
and esaft.
Trust. tac.
ebareholdt 3.5 La erat tLet
)
Pweaa engte make semi neesment*
sueurymfr Act ascTiost:Section 8(f).
appilcar should esteeinto 2",,e:J"e_, h W i g bei,,s.m me.eg.,,essue.ee u,}
.u s n o,.,,uoAvian:Appuoani 4,s== stian.
- di>=ciare consid-d.
t osatt
.,4.deaara ami n 6.
==s aber Sm s. Se inv=tment e
e the
.. e., be sue to
.e. sed a 6e.n messa.,m.: o spar.
- Ecut ami trac **. *. ad
'=t**'='
e.
.yinese the w e. a. ie se s uso d e anatisig ptase dates: W bcmdenwu Aled sing Fund.
. On >aa 30.1 um pkeure. and televiaAme onmeras during this e, y,,,1 an,,,,
a.a on y
8' g,g,'
statement trith the I a.nd ensetteig sne of b q'y be lireited to seleceed pertasma es deserunimod by the MA81eee oft lemCATIose SF mfmet:An prory meterish to its l
dare opproxime'tely a montS Dealiseen, se est asiae
.M ngardneg no tiene to order the licatica wiH be later.Da A
- 6e awa.ed isso useos as e,4.e. 6e-a
,6e,,3ade,pr0 21,1995. spplice6.t's bros.c.
- e w am. *
,eo,,.wa,s,pp,, red.e mie,.sted 6e. w.6,pereo. m o m* n erm a n g Acas "d,T,, y"b? g,
- w e,rma e
u.es.y'g, m. e,
- hormry and ser. vies pptkant with a as-.-,seaj,a' a
i a,,,
..ae i, m:,:rs.,,
, as e.ee,.e e,
,eae,
- gar
>w -i. e-,,,gu, br ad g; a-~
M"J",o' M1""". m'e.""e", now D ' E *br u op.m.
e f,d,':ent"ld ion,,e:"syt.e::
d e..t.e seme.e.;m e
?.
, v ea ~u., we w.e.a a A,ru e.i a r mod.6.uid be mevw--
noonapanied by proof of savios en eeuws J
pa neog'g 5
UNITE ~) STAT ES
/'
NUCLEAR RESULATORY COMMISSION n
{
l ADVISOMY COMMITTEE ON REACTOR SAFEGUARDS wash WGT ON, D. C. 30K5
/
1) 8:30 -
8:N A.M.
Ooenina Remarks by the ACRS ChairmRD (Open) 1.1)
Opening Statement (RLS/SD) 1.2)
Items of current interest (RLS/JTL/SD) 1.3)
Priorities for preparation of ACRS reports (RLS/SD) 2)
8:4f -
9: N A.M.
Procosed Reaulatory Accroach Associated with Steam Generator Intearity (Open) (RLS/NFD) 2.1)
Remarks by the Subcommittee Chairman 2.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed regulatory approach for dealing with steam generator integrity issues.
Representatives of the nuclear industry will participate, as appropriate.
0 $b
'fl3D jf$ t@lfd lY'$1/-f 9:g-10:0fA.M.
- BREAK ***
! ansecuences of Reactor Water Cleanuo System 3) 10:g-15: 30 P.M.
f Line Break Outside Containment (Open)
(JJB/MME) 3.1)
Report by the Subcommittee Chairman 3.2)
Briefing by and discussions with representatives of the tac staff regarding.the status of the report of the study performed by the staff on 3
the consequences of reactor water cleanup system line break outside containment.
Representatives of the nuclear industry will participate, as appropriate.
N gf,e ja g fela at.L >{ 4 < /wmq s
i.
4 2
- 4) 1h:30-11 A.M.
Subcommittee Reoort (Open) (TSK/PAB)
Report by the Chairman of the Thermal Hydraulic Phenomena Subcommittee regarding the items discussed during the March 28, 1997 subcommittee meeting.
/I'l7 -/l.' A 6th
- 5) -itT45 - 12 : 00 Noon Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et.al./
SD, et.al.)
Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in fj;p0 - ll:t/f b
M Of ' b I 'i
/Lt
- ll.'5p
)Y*<*,.tw &.. b), C!?$
hy
( L l. (4 -
1 :49 P.M.
- LUNCH ***
e'('4'I
';W ?
7 II.$) ~
l$~
2 k P.M.
! rooosed Reaulatory Guidance Related to 6) 1:
P Imulementation of 10 CFR 50.59 Recuirements (Open) (JJB/MTM) 6.1)
Remarks by the Subcommittee Chairman 6.2)
Briefing by and discussions with representatives of the NRC staff regarding the proposed regulatory guidance for assessing the adequacy of the licensees' process for implementing the requirements of 10 CFR 50.59, " Changes, Tests, and Experiments."
i Representatives of the nuclear industry will participate, as appropriate p;30.g'Sp NI.utSA4* bolf I10 "}
- l. M 2M-ST45-P.M.
- BREAK ***
b5 -
3 '!D 7) 4H45 -
6:46 p.M.
Precaration of ACRS ReDorts (Open)
J '/0
/S~
Discussion of proposed ACRS reports on:
7.1)
Shutdown Operations Risk (DAP/NFD) 7.2)
Proposed Regulatory Approach Associ-ated with Steam Generator Integrity (RLS/NFD) i 7.3)
Proposed Regulatory Guidance Related to Implementation of the 10 CFR 50.59 Requirements (JJB/MTM) 7.4)
Risk-Based Regulatory Acceptance Criteria for Plant-Specific Applica-tion of Safety Goals (TSX/NFD) f* M p #w,p/
- Pf5 9
e,
]p 3
IRIDAY, APRIL 4, 1997, CONFERMICE ROOM 2B3, 'nto WHITE FLINT NORTH, I
SOCEVILLE, MARYLAND 8) 8:30 -
8:35 A.M.
Ooenina Remarks by the ACRS Chairman (Open)
I (RLS/SD) 4'/I' 9) 0:35 - 1+r00+A.M.
Boraflex Dearadation in Soent Fuel Pool Storace Racks (Open) (TSK/NFD) 9.1)
Remarks by the Subcommittee Chairman 9.2)
Briefing by and discussions with representatives of the NRC staff regarding the resolution of issues associated with the degradation of Boraflex used in spent fuel pool storage racks and licensee responses to Generic Letter 96-04, "Boraflex Degradation in Spent Fuel Storage Racks."
Representatives of the nuclear industry will 4 participate, as appropriate.
(fl17. /0*Db
/.1}b's klAt ho 10:00 - 10:15 A.N.
- BREAK ***
JN9
/
- 10) 10 :15 - 11:49 A.M.
Ua.c of Potassium Iodide After a Severe i
Accident (Open) (RLS/AS) 10.1)
Remarks by the subcommittee Chairman 10.2)
Briefing by and discussions with the representatives-of the NRC staff regarding the NRC policy on the use of potassium iodide after a severe accident and other related issues.
Representatives of the nuclear industry will participate, as appropriate.
A 3D liitt -
1:15 P.M.
- LUNCH ***
l t lg.
):K biseawH$KZ.
11) 1 ($ -
Lees P.M.
Future ACRS Activities (Open) (RLS/SD)
J llh Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.
g jy- &W
,gf$ /b l b
.J.95
$ tt -
d L
p,-
4 12) 1:45 -
7:00 P.M.
Preoaration of ACRS Reoorts (Open)
(3:00-3:15 P.M. BREAK)
Discussion of proposed ACRS reports on:
12.1)
Shutdown Operations Riss (DAP/NFD) 12.2)
Proposed Regulatory Approach Associated with Steam Generator Integrity (RLS/NFD) 12.3)
Proposed Regulatory Guidance Related to Implementation of the 10 CFR 50.59 Requirements (JJB/MTM) 12.4)
Boraflex Degradation in Spent Fuel Pool Storage Racks (tentative)
(TSK/AS) 12.5)
Risk Based Regulatory Acceptance Criteria for Plant-Specific Applica-tion of Safety Goals (TSK/NFD)
.fi.J.m..jh/'/,RW SATtTEDAY. -Armas n, Ayyi. CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE,. MARYLAND 13)
Br$0 -
3.00 A.M.
Recort of the Plannina and Procedures j/;z///
f,. g f Subcommittee. (Open/ Closed) (RLS/JTL)
Reporc of the P)anning and Procedures Subcommittee on matters related to the conduct of ACRS business, qualifications
+
of candidates nominated for appointment to the'ACRS, and organizational and personnel matters relating to the ACRS.
[ Note:
A portion of this session may be closed to discuss organizational and personnel matters that relate solely to the internal personnel rules and practices of this Advisory Committee, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.)
10 )tnl. W 0 Ac ?S /a.H M l h' d 4 15 T'/b 14) 9: 0 - 12:00 Noon Precaration of ACR$ Recorts (Open)
(10:30 - 10:C5 A.M. BREAK)
Complete discuss n of proposed ACRS reports listed un rI m 12.
- 15) 12:00 -
1:00 P.M.
Stratecie-ann no (Open) (RLS/JTL)
Discussio of it a of significant importa e to NRC, neluding rebaselining of the ommittee act vities for FY 1997.
o*
5 16) 1:00 -
1:30 P.M.
Miscellaneous (Osen) (RLS/SD)
Discum on of scellaneous matters related to the e due of committea activities and matters an ecific issues that were not completed d ng previous meetings, as time and avail l '.,i t of information permit.
HQII:
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.
e Number of copies of the presentation materials to be provided to the ACRS - 35.
e
-r,-+
-g
-r e
o ec,-
r e-,-,+-m-w~
--e-wm~---
,r--
o.
APPENDlX lil: MEETING ATTENDEES 440TH ACRS MEETING APRIL 34,1997 NRC STAFF Thursday. April 3.1997 C. Ader RES F. Akstulewicz NRR P. Brother NMSS J.Donoghue NRR F. Eltawila RES R. Gallo NRR W. Jensen NRR A. Levin NRR S.Long NRR M. Malloy NRR L. Marsh NRR T. Martin NRR E.McKenna NRR J. Mitchell OEDO J. Murphy RES D. Persinko NMSS L. Plisco NRR T Scarbrough NRR M. Snodderly NRR D, Soldin NRR H. Walker NRR J. Williams NRR Friday. April 4.1997 M. Chatterion NRR G. Hubbard NRR L.Knopp NRR G. Hubbard NRR E. Manstein-AEOD J. Mitchell OEDO A. Mohseni AEOD D. Persinko NMSS J. Sped NMSS C. Trotter RES
.o Appendix lll 2
440th ACRS Meeting ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC Ihgrsday April 3,1997 S. Bernist WPSC
~
C. Callaway NEl C. Chapman Bechtel D.Chung NUS LIS J. Hoss TV Electric P. Lovett Shaw Pittman T. Pietrangelo NEl
' N. Oliver Shaw Pittman J. Trotter Polestar Applied Tech.
D. Walters NEl A. Wyche Bechtel Fridav. April 4,1997 D.Chung NUS LIS D. Meineist Copley News Services A. Nelson NBI R, Wight II. Dept. Of Nuclear Safety i
.,__.,w, w
v.__..
-r,-
...,. ~
-y--
v-r,
s.
APPENDlXIV: FUTURE AGENDA The Committee agreed to consider the following during the 441st ACRS Meeting, May 1 3, 1997:
THURSDAY..MAY 1,1997 1) 8:45 A M - 10:30 A M.: Design Basis Verification (Open)- The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposud memoranda to the Commission associated with review criteria for design basis verification and other related NRC staff activities.
2) 10:45 A M - 11:45 A MJ Electric Utility Restructurina and Dereaulation (Open)-
The Committee will hear presentations by and hold discussions with representatives of the NRC Staff regarding the proposed final Policy Statement on restructuring and economic deregulation of the electric utility industry.
3) 1:00 P.M. - 2:00 P MJ Proposed Final Reaulatory Guide 1.164. " Time Response Deslan Criteria for Safetv Related Operator Actions"(Open)- The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed final Regulatory Guide 1.164.
4) 5:15 P.M - 7:00 P M : Preparation for Meetina with the NRC Commissioners (Open) - The Committee will discuss the following items in preparation for meeting with the NRC Commissioners on May 2,1097:
a) risk informed, performance-based regulation and risk based regulatory acceptance crl-teria for plant specific application of safety goals; b) proposed regulatory approach associated with steam generatcr integrity; c) shutdown operations risk; d) status of ACRS review of National Academy of Sciences / National Research Council Phase 2 study on digital instrumentation and control systems; e) Human Performance Program Plan; and f) ACRS repor1 to Congress on Nuclear Safety Research and Regulatory Reform.
FRIDAY. MAY 2.1997 5) 9:00 A M. - 10 30 A Ma Meetina with the NRC Commissioners -
Commissioners' Conference Room. One White Flint North - Meeting with the NRC Commissioners to discuss the following items:
a) risk-informed, performance-based regulation and risk based regulatory acceptance cri-teria for plant specific apphcation of safety goals; b) proposed regulatory approach associated with steam generator integrity; c) shutdown operations risk; d) status of ACRS review of National Academy of Sciences / National Research Council Phase 2 report on digital instrumentation and control systems; i
l i
... :s i
Appendix IV 2
440th ACRS Meeting
- 5) Human Performance Program Plan; and i
- 6) ACRS report to Congress on Nuclear Safety Research and Regulatory Reform.
~
i i
i
}
l I
1 s
)
?
f 3
B
.,-re
-.~.-
.,y..w-----
r-+~
.-----v-w-
-..~,-m,-w%ye,*,.----,...,.-r.w.-,+e w
- ---+-P r
r,-
- -*-T e
s w w' v e " * *
+'w a
- - + -=
--+-v--+.-----'
wi.b<-"-a
~
APPENDlX V i
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 l TEM NO, 1
Openina Remarks by the ACRS Chairr tr}
1.
Items of Interest,440th ACRS Meeting, dated April 3 5,1997 2
Proposed Reoulatory Acoroach Associated with Steam Generator Inteority 2.
Steam Generators, dated April 2,1997, presented by Jack R. Strosneider, Division of Engineering, NRR [Viewgraphs) 3 Consecuences of Reactor Water Cleanuo System Line Break Outside Containment 3.
Reactor Water Cleanup System (RWCS) Pipe Break Study: Background -
Study Approach - Key issues - Status, dated April 3,1997, presented by Ronald M. Young, Plant Systems Branch, NRR [Viewgraphs) 4 Subpommittee Report 4.
Summary of March 28,1997 Thermal Hydraulic Phenomena Subcommittee Meeting [ Handout) [May contain Proprietary Material Authorization Required Prior to Release) 5.
Report of ACRS Consultant Dr. Ivan Catton on the March 28,1997 Thermal.
Hydraulic Phenomena Subcommittee Meeting [ Handout) (May contain Proprietary Material - Authorization Required Prior to Release) 6.
Summary of Report: Probability of Steam Generator Tube Failure during a Severe Accident, undated, prepared by Dr. Ivan Catton.
5.
Reconciliation of ACRS Commants and Recommendations 7.
Reconciliation of ACRS Comments and Recommendations [ Handout #5.1)
Appendix V 2
440th ACRS Meeting 6
Proposed Reaulatory Guidance Related to lmolementation of 10 CFR 50,59 Reauirements 8.
10 CFR 50.59 Regulatory Procesa Improvements, dated April 3,1997, presented by NRR 9
Boraflex Dearadation in Soent Fuel Pool Storace Raskt i
9.
Boraflex Problem in Spent Fuel Storage Pools, dated April 4,- 1997, presented by Laurence Kopp, DSSA, RES [Viewgraphs) 10 Use of Potassium lodide After a Severe Accident 10.
RES Proposed Resolution to Petition for Rulemaking (P.M. 50-63) to Require Availability of Potassium lodide for Use by the General Public After t
an Accident, dated April 4,1997, presented by Mike Jamgochlan, RES 11.
Stockpile of Potassium lodide and Use by the General Public in a Radiological Emergency, dated April 4,1997, presented by Alan Nelson, Nuclear Energy Institute (Viewgraphs) 12.
Policy on issuance of Potassium lodide Coincident with Nuclear Power Accidents, dated April 4,1997, presented by Roy R. Wright, Manager, Office of Nuclear Facility Safety, State of Illinois [Viewgraphs) 13.
Memorandum to the ACRS, dated March 26,1997, from Peter Crane,
Subject:
Potassium lodide (KI)[ Handout) 11.
Future ACRS Activities 14.
Future ACRS Activities - 441st ACRS Meeting, May 1-3,1997 [ Handout
- 11.1]
13.
Report of the Plannina and Procedures Subcommittee
- 15. -
Final Draft Minutes of Planning and Procedures Subcommittee Meeting -
April 2,1997 [ Handout #13.1)
e.
cp Appendix V 3
440th ACRS Meeting MEETING NOTEBOOK CONTENTS
. TAR DOCUMENTS 2
Proposed Reautatory Anoroach Associated with Steam Generator Intearity 1.
Table of Contents 2.
Proposed Agenda, April 3,1997 3.
Status Repor1, dated April 3,1997 (Internal Committee Use Only:
Predecisional Material Attachedj 4.
Memorandum, dated February 24,1997, from L. Joseph Callan, Executive Director for Operations (EDO),
Subject:
Stearn Generator Rulemaking 3
Consecuences of Reactor Water Cleanuo Sys;em Line Break Out. side Containment 8.
Table of Contents 9.
Proposed Schedule, April 3,1997 10.
Status Report, dated April 3,1997 11, Letter dated July 13,1994, from T. S. Kress, Chairman, ACRS, to James M.
Taylor, EDO,
Subject:
Some Areas for Potential Staff Consideration for Operating Nuclear Power Plants and the Review of Future Plant Designs Resulting from the ACRS Review of the Evolutionary Light Water Reactors 12.
Letter dated February 15,1995, from T. S. Kress, Chairman, ACRS, to James M. Taylor, EDO,
Subject:
Reactor Water Cleanup System Line Break for Operating BWRs 13.
Letter dated September 9,1994, from James M. Taylor, EDO, to T. S. Kress, Chairman, ACRS, Subject. Some Areas for Potential Staff Consideration for Operating Nuclear Power Plants and the Review of Future Plant Designs Resulting from the ACRS Review of the Evolutionary Light Water Reactors 4
S_p,bcommittee Report 14.
Table of Contents 15.
Project Status Report 16.
Letter dated March 4,1997, from W. C. Huffman, NRR, to Nicholas J.
Liparuto, Westinghouse Electric Corporation,
Subject:
Request for Additional Information on the WCOBRA/ TRAC Oregon State University (OSU) Long-Term Cooling (LTC) Final Validation Report 6.
Proposed Reoulatorv Guidance Related to implementation of 10 CFR 50 59 Reouirements
s a.
e Appendix V 4
440th ACRS Meeting 17.
Table of Contents 18.
Proposed Schedule, April 3,1997 19.
Status Report, dated April 3,1997 20..
Viewgraphs from Cammission Briefing on 10 CFR 50.59 Process Improvements, March 10,1997 21.
SECY 97 035, " Proposed Regulatory Guidance Related to implementation of 10 CFR 50.59 (Changes, Tests and Experiments) 9.
Boraflex Deoradation in Soent Fuel Pool Storaae Racks 22.
Table of Contents 23.
Proposed Agenda, April 4,1997 24.
Status Report, dated April 4,1997 25.
NRC Generic Letter 96 04, dated June 26, 1996,
Subject:
Boraflex Degradation in Spent Fuel Pool Storage Racks 26.
Memor&ndum to the Commission from James M. Taylor, EDO, dated October 2,1996,
Subject:
Response to Staff Requirements Memorandum dated August 27,19% - Briefing on Spent Fuel Pool Cooling issues j
10.
Use of Potassium lodide After a Severe Accident
[
27.
Table of Contents 28.
Proposed Schedule, April 4,1997 29.
Status Repor1, dated April 4,1997 30.
Memorandum dated February 13,1997, from Bill R. Morris, Office of Nuclear Regulatory Research, to John T, Larkins, Executive Director, ACRS,
Subject:
ACRS Review of the Denial of Petition for Rulemaking (PRM 50-63) Relating to a Re evaluation of the Policy Regarding Use of Potassium lodide After a Severe Accident at a Nuclear Power Plant g
1 7
-=
m-r-
-- - - - -== -