ML20141A504
| ML20141A504 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim, 05200003 |
| Issue date: | 04/04/1997 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20141A507 | List: |
| References | |
| ACRS-3055, NACNSRRC, NUDOCS 9705140338 | |
| Download: ML20141A504 (20) | |
Text
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CERTIFIED f/
R. L. Seale, Chairman
- o April 15, 1997 g?d23-8655
\\
April 4, 1997
SUMMARY
/ MINUTES OF THE ACRS PLANNING AND PROCEDURES SUBCOMMITTEE MEETING APRll 2, 1997 The ACRS Subcommittee on Planning and Procedures held a meeting on April 2,1997, in Room 2B1, Two White Flint North Building, Rockville, Maryland. The purpose of the meeting was to discuss matters related to the conduct of ACRS business.
The meeting was convened at 1:30 P.M. and adjourned at 3:45 P.M.
ATTENDEES R. L. Ser?e, Chairman D. A. Po ;rs T. S. Kress ACRS Staff 4
J. T. Larkins, ACRS Executive Director S. Duraiswamy 4
C. Harris R. Savio R. Summers 1)
DOCUMENTS REFERRED TO IN ACRS REPORTS / LETTERS Certain documents were referred to in the report to Chairman Jackson approved by the full Committee 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 them had not been distributed to ACRS Members, nor to the staff. Members are reminded to distribute supporting documents well in advance so all Members vill "have benefit of the documents referenced" before reports or letters are approved.
(Carried over from March 5, 1997.)
RECOMMENDATION The Subcommittee recommends 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 members prior to the meeting
/(gof at which such a report or letter is written. A further check will be made during the finil
- iew of the draft report or letter prior to presenting it for final ap
,0.
t t) il RECOMMENDATION 2)
PRIORITIES FOR THE REMAINDER OF FY 1997 Ob El ~ h [" N 7
Dr. Seale has prepared a list of priority ACRS issues for the remainder of CY 1997, which he will discuss at the Atomic Safety and Licensing Board g 51 g 8 970404 3055 PDR DESIcNATED ORIGINAL lli!Illiiiiii!Ejll!!)11 ce.mm e,
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Panel Meeting later this month.
If the Committee can agree that the attached list (p. 4) 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.
RECOMMENDATION The Subcommittee recommends that this list be reviewed and approved after 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 is attached (pp. 5-10).
The planned ACRS activities are substantial and as a result, it is suggested that we should prioritize issues for Subcommittee meetings.
I RECOMMENDATION The Subcommittee recommends that the staff indicate 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 HEETINGS IN CY 1996 An evaluation of time spent by the Committee during the full Committee meetings in CY 1996 is attached (pp. 11-19).
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 recommends that the staff continue to track how the Committee utilizes its time and periodically provide this 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.
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 implement each of +he strategic initiatives.
Funds for these strategic initiatives must come from cuts in other areas.
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7)
INTERNATIONAL ACTIVITIES A fax message was received from_Dr. Birkhofer,'RSK, (p. 20) on March 11, 1997, stating that he would be available in late October for the Quadripartite Meeting.- A fax message was sent on_ March 24,1997, to Dr. Togo, STA, requesting information concerning the Quadripartite Meeting (p. 21).
A reply to this fax was sent by Mr. Asakawa (ps r
- 22) saying that the Japanese cannot have the meetin'g in October and j
prefer the date of January 12-16 or 19-23,1998.
RECOMMENDATION The Subcommittee recommends that. the Members determine the i
i 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.
1 Discussions are continuing with RSK on the joint ACRS/RSK meeting on i
April 30. ACRS Members will be assigned agenda topics to discuss.
l A copy of the proposed final _ agenda is attached (pp. 23-24).
/
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RECOMMENDATION The Subcommittee recommends that Members review the agenda, including their assigned topics, and approve a final agenda.
l 8)
NUCLEAR SAFETY RESEARCH REVIEW COMMITTEE j
A report by the Nuclear Safe'ty Research Review Committee, dated January 15, 1997, is attached (pp. 25-36).
'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 (pp. 37-39), and a Memorandum to the Commission from L. Joseph Callan, Executive Director for Operations, dated March 13,.1997 (pp. 40-41), also address the subject'of ACRS/NSRRC coordination..Some response to these documents may be advisable.
- RECOMMENDATION The Subcommittee recommends that Members discuss these documents and the appropriate response.
9).
MEMBERS' ISSUES A memorandum from Dr. Powers (pp. 42-43) records his observations of the revised procedures for letter-writing during the March ACRS meeting.
RECOMMENDATION The Subcommittee recommends that Members read'and comment on Dr.
Powers' memorandum and provide additional comments on how the new h,
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. gv procedures are working, as appropriate.
A memorandum from Dr. Powers (pp. 44-45) recommends that ACRS review the Nonconservative Operations During Isolation of a Reactor i
Recirculation. Pump Seal Leak at the Clinton Power Station.
RECOMMENDATION The Subcommittee recommends that Dr. Powers, Dr. Apostolakis, and i
Mr. Barton develop a way of tracking those events that involve human factors and other operational issues for future review, A memorandum from Dr. Powers (pp. '46-50) identifies research topics a
and recommends that time be set aside at a future meeting to discuss this topic.
RECOMMENDATION i
The Subcommittee recommends that the Committee continue to collect topics to be reviewed with the Director of the Office of Nuclear
^
Ree.latory Research.
i 10)
TRAVEL f
' Requests were received from Drs. Kress and Fontana to attend the American Nuclear Society meeting in Orlando, FL. on June 1-4, 1997 (pp. 51-52).
i A request was received from Dr. Miller to. attend one day of a workshop on Nuclear Utilities Software in Bloomington, Il on May 7, 4
1997 (pp. 53-56).
A request was received from Dr. Apostolakis to attend a meeting with t
senior INP0 management on PRA in Atlanta, GA on April 14-15, 1997 (pp. 57-58).
i RECOMMENDATION The Subcommittee recommends that all four requests for travel be approved.
y.
J PROMIU1DT IOOUD LIOT NEZT TWO YEARS j
i EDT BUTTON ISSUES RISE INFm uun, PERFORMANCE - EASED REGULATION 2
SAFETY RE8E&RCE PROGRAM i
CERTIFIchTION OF AP600
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SAFETY GOAL POLICY IMPLEMENTATION i
I SAPETY REL&TED RULES,REGUL&TIONS, POLICY MATTERS,AND i
REGUL& TORY GUIDES
}
l 1
FIRE PROTECTION EIGE BURNUP FUEL.S I
EUMAN FACTORS AND ORGANIRATIOEAL FACTORS i
i, RECURRING ISSUES 8
j DIGITAL INSTRUNENTATION AND CONTROL I
LICENSE RENEWAL T m uu,,NYDRAULIC PRENOMEMA 1
j PLANT OPERATING EXPERIENCE l
MATERIALS AND METALLURGY 1
i AN UNOPENED BOX i
l REVIEW OF DOE ACTIVITIES l
r i
l 1
I
1997 ACRS SCHEDULE - MONTHLY TOTALS (Summary)
- 02. ape.97 MEETING MONTH NUMBER OF FULL NUMBER OF TYPE COMMITTEE SUBCOMMITTEE SESSIONS MEETINGS FULL 01-Jun-97 7
01-Jul-97 7
01-Sep-97 8
01-Oct-97 4
01-Nov-97 5
01-Dec-97 5
01-Feb-98 4
01-Mar-98 2
01-Apr-98 3
FULL 45 SUB 01-Jun 97 2
01-Jul-97 5
01-Aug-97 6
01-Sep-97 5
01-Oct 97 5
01-Nov-97 2
01-Dec-97 2
01-Jan-98 1
01-Feb-98 1
01-Mar-98 1
SUB 30 Grand Total:
45 30 1
1997 ACRS SCHEDULE - NUMBER OF SUBCOMMITTEE MEETINGS 4/2/9 ISSUE Row Summary 6/1/97 7/1/97 8/1/97 9/1197 10/1/97 1111/97 1211/97 111/98 21119 8 3/1/98 AP600 5
1 1
1 1
1
,AP6_00 TAP 7
1 2
2 1
1 p
EXTERNAL PHENO 1
FIRE PROTECTION 2
__ _1.
FUEL STORAGE GSI HIGH BURNUP FUEL 2
1 1
HUMAN FACTORS 1
1 I&C LIC. RENEWAL 2
1 1
M&M 2
1 1
MEETING PLANT OPS 2
1 1
PRA 2
1 1
RELIABILIT( DATA 1
1 RPT TO CONGRESS RX FUELS SAFEGUARDS SD OPS RULE 1
1 SEVERE ACCIDENT 1
1 T-H 2
1 1
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l 1997 ACRS SCHEDULE - BY DATE 02-Apr.97 MEETING DATE TYPE MEETING 01-Jun-97 FULL B-17, TIME RESPONSE ECCS SUCTION HEAD GL - SHUTDOWN LOCA GL - STRAINER BLOCKAGE l&C SRP/RG l
METAL FATIGUE SPENT FUEL SAFEGUARDS SUB AP600 TAP SCALING /PIRT FITNESS FOR DUTY 01-Jul-97 FULL FITNESS FOR DUTY HALDEN PROJECT HIGH BURNUP FUEL MAINE YANKEE LESSONS LEARNED MEETING WITH EDO RASCAL CODE SElSMIC HAZARD ANALYSIS SUB AP600 TAP LOFTRAN (V&V)
FIRE PROTECTION RISK-BASED ANALYSIS HIGH BURNUP FUEL RES CRITERIA NOTRUMP (V&V)
STRAINER CLOGGING 01-Aug-97 SUB AP600 CHAP 6-10 AP600 TAP PCCS TEST + ANALYSIS LONG-TERM COOLING RELIABILITY DATA 1
MEETING l
DATE TYPE MEETING RES TH CODE UPGRADE SG TUBES 01-Sep.97 FIILL 1&C RG INSTRUMENT SETPOINTS I&C RG LIGHTNING PROTECTION
)
l LER GUIDANCE MEETING WITH DEPUTY EDO NON-POWER SURVEY RELIABILITY DATA 1
SA MANAGEMENT PLANS SALEM RESTART SUB AP600 CHAP 12,13,16 AP600 TAP LONG-TERM COOLING LIC RENEWAL TOPICAL REPORTS SEVERE ACCIDENT MANAGEMENT SITE VISIT AND MEETING 01-Oct-97 FULL AP600 TAP PCCS FIRE PROTECTION AND PRA MEETING WITH NRR DIRECTOR i
PART 55 RO/SRO EXAMS SUB i
10 CFR 50.55a AP600 CHAP 14,15, PRA AP600 TAP PCCS TEST + ANALYSIS LIC. RENEWAL EVAL. SITE VISITS MAINE YANKEE SB LOCA CODE 01-Nov 97 FULL 10 CFR 50.55a LIC. RENEWAL MEETING WITH COMMISSION RG QUAL. + TRAINING
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MEETING DATE TYPE MEETING RPT TO CONGRESS SUB FIRE PROTECTION SRP/I'EG. GUIDE 01-Dec-97 FULL FIRE PROTECTION FUEL STORAGE CRITICALITY METH MEETING WITH RES DIRECTOR MILLSTONE RESTART PRA SRP/RG SUB AP600 FSER HIGH BURNUP FUEL 01-Jan-98 SUB AP600 FSER 01-Feb-98 FULL AP600 FSER ASME PIPING CODE COM. GRADE DEDICATION MEETING WITH AEOD DIRECTOR SUB FIRE PROTECTION 01-Mar-98 FULL AP600 FSER MEETING WITH NMSS DIRECTOR SUB i
SD OPS RULE 01-Apr-98 FULL BWR POWER UPRATE RG DOSIMETRY METHODS 3
MEETING i
DATE TYPE MEETING SD OPS RULE 4
le
ACRS MEETINGS _Crosstabi 4/1/97
~dctivity SumOfHours 428 429 430 431 435~ 433~l 34
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5~ 35f 435 43 Commissioners 23 4.9 2.2 2.7 Future Activities 3g 5.3 0.6 1
0.8 0.3 0.5 0.4 0.2 0.5 0.4 0.6 Information item
/6 7, 34 2.7 1.1 4.8 1.9 5.2 2.6 5.2 3.1 2.7 4.7 Opening Remarks i 7, 2.6 0.2 0.4 0.2 0.2 0.2 0.3 0.3 0.3 0.3 0.2 P+P Report 5 'I 10.4 0.5 2.7 0.8 1.5 0.8 0.6 0.9 0.7 0.8 1.1
~
Reconciliation a7 3.4 1.2 0.1 0.1 0.2 0.7 0.2 0.1 0.1 0.7 Report / Letter afg 7, 102.2 7.8 11.1 10.2 10.1 12 11.3 3.6 14.3 14 7.8 Review item 23'4 47.9 8.5 7.4 4.9 3.6 3.7 ' 6.1 3.5 3.5 3.3 3.4 5trategic Planning 0.5 0.5 i
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ACRS 1996 Report (Summary)
OI Apr.97 Activity Project Description Hours Commissioners 4.9 Commissioniers 4.9 2.32 %
Future Activities 5.3 Future Activities 5.3 M.1%
information item Browns Ferry restart 1.5 Certification of Evolutionary Designs 0.4 Control Room Fire at Palo Verde 0.6 l
Emergency Planning for Advancad Reactors 1.1 Graded Quality Assurance Program 1.5 Health effects of low-levels of ionizing radiation 2.9 Human Performance Program Plan 1.7 Implementation Guidance for License Renewal 1.2 Indian Point restart 1.9 IPE Insights Report 1.5 Loss of feedwater event at ANO-1 1.3 Loss of offsite power at Catawba 0.8 Meeting with AEOD Director 1.s Meeting with RES Director 2
N2 Bubble in Reactor Coolant System 1
NRC Emergency Response Program 1.5 NRC Strategic Assessment and Rebaselining Effort 2.3 Plant Aging Research Program 1.7 Reactor Vessel Annealing 1.1 Research program for l+C Sysrtems 1.5 Rulenet 0.9 Spent fuel pool cooling issues 2.6 Spent Fuel Project Office Activities 0.6 1
/r 0
_. ~.. _ _
l Activity Project Description i
Hours I
Used of Revi:ed Source Term 0.6
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Information Item 34 16.10 %
i Opening Remarks 1
26 Opening Remarks 2.6 1.23 %
P+P Report 10.4 P+P Report 10.4 4.92 %
Reconciliation 3.4 Reconciliation 3.4 1.61 %
Report / Letter 10 CFR Parts 50 + 100, Reactor Site Criteria 2
Adequacy of Code to Analyze SG Tubes 10.4 Adequacy of Individual Plant Examinationa 1
Annual Report to Congress 4
' Appointment of new members
1.5 Bulletin
Recirculation Sump Strainer Clogging Event 2
Conformance of Operating Plants to Safety Goals 2
Design Changes to ABWR Design 1.5 Design Changes to CE System 80+ Design 1.5 Digital l+C Systems 7
Draft RG associated with license renewal 3.5 DSI-22, Future Role of NRC Research 1.5 GSI-78 Metal Fatigue 1
Health effects of low-levels of ionizing radiation 0.5 Human Performarice Program Plan 5.8 IPE Insights Report 3.5 NRC Thermal Hydraulic Codes 4.3 Plant-Specific Application of Safety Goals 3.5 2
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- 3..-
Activity-Project Description Hours Potential Use of IPE to Compare with Safety Goals I
PRA Fire Model 2
PRA Framework and Use of PRA in Regulatory Process 2
Proposed Rule on SG Integrity 4
Regulatory Review Group 0.6 RELAP/ MOD 3 Code for AP600 Design 3
Resolution of MSRP lasues 2
1 Rev 2 to GR 1,149 Simulation Facilities Used in Examinations 1
d Risk Based Analysis of Reactor Operating Experience 3.5 Risk-Informed, Performance Based Regulations 5
SECY-128 Policy issues For AP600 Design 2
Severe Accident Research 7.5 Shutdown Operations Rule 2
SRP for Dry Cask Storage 0.2 US Membership in NEA 1.5 Use of IPE in Regulatory Process 3.6 Westinghouse COBRA / TRAC Best-Estimate T/H Code 4.8 Report / Letter 102.2 48.39 %
Review item 10 CFR Parts 50 + 100, Reactor Site Criteria,
2.2 Adequacy of Code to analyze SG Tubes 3.5 Adequacy of Individual Plant Examinations 2.2 Digital l+C Systems 3.1 Draft RG associated with license renewal 1.5 Fire Protection issues 1.2 GSI-78 Metal Fatigue 0.7 Human Performance Program Plan 1.7 IPE Insights Report 1.2 lssues associated with steam generators 1
NRC Thermal Hydraulic Codes 2
Probabilistic Risk Assessment 2.3 Proposed Rule on SG integrity 2.1 Recirculation Sump Strainer Clogging Events 3.1 3
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Activity Project Description Hours Regulatory Review Group 05 RELAP/ MOD 3 Code for AP600 Design 1.8 Rev 2 to RG 1.149 Simulation Facilities Used in Examinations 1
RG on I&C Systems 1.4 Risk-Based Analysis of Reactor Operating Experience 1.2 Risk-Informed, Performance Based Regulations 1.4 l
SECY-128 Policy lasues For AP600 Design 2.7 Severe Accidents, codes for SG rule 1.1 Shutdown Operations Rule 1.3 j
SRP and Reg. Guide for risk-informed, pefromance based regu 1.7 Supplemental SERs for evolutionary plant designs 2
Westinghouse COBRA / TRAC Best-Estimate T/H Code 3.8 Review Item 47.9 22.68 %
Strategic Planning 0.5 i
Strategic Planning 0.5 0.24 %
Grand Total:
211.2 l
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l' ACRS MEETINGS 4/1/g l
Meet Date l Activity l~
Project Description (Hours ~
l 428 2/8/96 Review Item Recirculation Sump Strainer Clogging Even!
3.1 428 2/8/96; Review item Westinghouse COBRA / TRAC Best-Estimatl 2.2 428 2/8/96l Report / Letter Annual Report to Congress 0.5 428 2/8/96 Report / Letter Adequacy of Individual Plant Examinationa 1
428 2/8/96 Review item Adequacy of Individual Plant Examinations 2.2 428 2/9/96 Future Activities 0.6 428 2/9/96' Opening Remarks 0.2 428 2/9/96,P+P Report 0.5 428 2/9/96 Report / Letter Rev 2 to GR 1.149 Simulation Facilities Us 1
428 2/9/96: Report / Letter Bulletin: Recirculation Sump Strainer Clogg.
2 428 2/9/96' Review item
.Rev 2 to RG 1.149 Simulation Facilities Us; 1
428 2/9/96 Reconci!iation l
1.2 428 2/9/96Information item ilmplementation Guidance for License Rene!
1.2 428 2/9/96Information item ! Human Performance Program Plan I
1.5 428 2/9/96 Report / Letter fNestinghouse COBRA / TRAC Best-Estimat!
3.3 429 3/7/96_P+P Report 1.8 429 39/961nformation item lReactorVessel Annealing 1.1 429 1 3/7/96' Review Item
!RG on l&C Systems I
1.4 429 i 3/7/96l Opening Remarks j
0.4 429 ! 3/7/96 Review Item
! Fire Protection issues l
1.2;
~
429 3/7/96 Review Item lRELAP/ MOD 3 Codelor ~PID0 Design ~
i E8' 429 3/8/96 Review Item
'Probabilistic Risk Assessment 2.3 i
429 3/8/96 Report / Letter GSI-78 Metal Fatigue 1
429 3/8/96 Report / Letter Resolution of MSRP issues 0.5 429 ! 3/8/96 Report / Letter
,RELAP/ MOD 3 Code for AP600 Design 3
l 429 3/8/96 Report / Letter lPRA Fire Model 2
429 3/8/96lP+P Report I
0.9 429 3/8/96 Reconciliation i
1 0.1 429 3/8/96 Future Activities l
l 1
429 3/8/96_ Review item GSI-78 Metal Fatigue 1
0.7 429 3/9/96 Report / Letter Potential Use of IPE to Compare with Safet 1
429 3/9/96 Report / Letter Use of IPE in Regulatory Process 3.6 429 3/9/96 Strategic Planning I
0.5 430 4/11/96l Review item Severe Accidents, codes for SG rule 1.1 430 4/11/96;lnformation Item Graded Quality Assurance Program 1.5 430 4/11/96' Review Item Westinghouse COBRAURAC Best-Estimat 1.6 430 4/11/96, Opening Remarks 0.2 430 4/11/96' Review Item
.10 CFR Parts 50 + 100, Reactor Site Criteri 2.2 430 4/12/96.Information item Meeting with AEOD Director 1.8 430 4/12/96' Future Activities 0.8 430 4/12/96l Report / Letter 10 CFR Parts 50 + 100, Reactor Site Criteri' 2
i A30 I 4/12/96' Report / Letter Severe Accident Research l
1.5 i
l i,
ACRS MEETINGS 4/1/9 Meet l Date l Activity l
Project Description l Hours 430 4/12/96. Report / Letter lPRA Framework and Use of PRA in Regul I 2
430 4/12/96 Report / Letter Westinghouse COBRA / TRAC Best-Estimat 1.5 430 4/12/96.P+P Report 0.8 430 4/12/96Information item Rulenet 0.9 430 4/12/961nformation item Spent Fuel Project Office Activities 0.6 1
430 4/12/96l Report / Letter SRP for Dry Cask Storage 0.2 430 4/12/96; Report / Letter US Membership in NEA 1.5 430 4/12/96 Report / Letter Appointment of new members 1.5 1
431 5/23/96; Review Item Regulatory Review Group 0.7 431 5/23/96,Information item IPE Insights Report 1.5 431 5/23/96l Opening Remarks 0.2 431 5/23/96 Review item Shutdown Operations Rule 1.3 431 5/23/961nformation item Certification of Evolutionary Designs I
0.4, 431 5/23/96l Review item Digital l+C Systems 1.6 431 5/24/96l Reconciliation I_
0.1 431 5/24/96 P+P Report 1.5 431 5/24/96 Future Activities 0.3 431 5/24/96 Commissioners 2.2 431 5/25/96l Report / Letter l Shutdown Operations Rule 2
431 5/25/98 Report / Letter l Resolution of MSRP lssues 1.5 431 j 5/25/98_ Report / Letter Regulatory Review Group 0.6 l
431 5/25/96l Report / Letter Severe Accident Research i
2
'431 5/25/96 Report / Letter Conformance of Operating Plants to Safety 2
431 5/25/96 Report / Letter Digital l+C Systems 2
432 6/12/96l Report / Letter Health effects of low-levels of ionizing radiai 0.5 432 6/12/96 Report / Letter Adequacy of Code to Analyze SG Tubes l
0.5 432 6/12/96. Report / Letter
!IPE Insights Report 3.5 432 6/12/96_Information item ! Loss of offsite power at Catawba 0.8 432 6/12/96 Report / Letter jSevere Accident Research I
4 j
432 ' 6/12/96.Information item ! Health effects of low-levels of ionizing radia 2.9 432 ! 6/12/96 Reconciliation 0.2 1
432 16/12/961nformation item Browns Ferry restart 1.5 432 6/12/96 Review Item issues associated with steam generators 1
432 6/12/96 Report / Letter Draft RG associated with license renewal 3.5 432 6/12/96 Future Activities 0.5 432 6/12/96; Review item IPE Insights Report 1.2 432 6/12/96 Review item Draft RG associated with license renewal 1.5 432 6/12/96 Opening Remarks 0.2 432 l 6/12/96P+P Report 1
0.8 433 l 8/8/96 Review item Supplemental SERs for evolutionary plant i 2
433 l 8/8/96 Review Item SECY-128 Policy issues For AP600 Desig !
2.7
~
433 i 8/8/96_ Review Item
_ Risk-Informed, Performance Based Regula !
1.4 l'I
ACRS MEETINGS 4/1/9 Meet Date l Activity l
Project Description l Hours r
433 8/8/96; Opening Remarks I 0.3 433 8/9/96; Reconciliation 0.7 433 8/9/96;P+P Report 0.6 433 8/9/96;lnformation item Spent fuel pool cooling issues 2.6 433 8/9/96; Future Activities 0.4 433 8/10/96; Report / Letter Design Changes to CE System 80+ Design 1.5 l
433 8/10/96; Report / Letter Design Changes to ABWR Design 1.5 433 8/10/96 Report / Letter Risk-Informed, Performance Based Regula 5
433 8/10/96l Report / Letter SECY-128 Policy issues For AP600 Desig 2
433 8/10/96l Report / Letter Adequacy of Code to Analyze SG Tubes 1.3 434 9/12/96'Information Item Indian Point restart 1.9 434 9/12/96_ Review Item Adequacy of Code to analyze SG Tubes 3.5 434 9/12/96' Reconciliation 0.2 434 9/12/96;P+P Report t
0.9 434 9/12/96 Future Activities 1
0.2 434 9/12/96 Opening Remarks t
0.3 434 9/13/96_Information item,Loss of feedwater event at ANO-1 1.3 434 9/13/96 Report / Letter lAdequacy of Code to analyze SG Tubes 3.6 i
434 9/13/96.Information item Meeting with RES Director 1
2
.435 0/10/96_ Review Item
_ Digital l+C Systems i
1.5 435 i 0/10/96 Reconciliation l
0.1 435 ! 0/10/96 Future Activities i
0.5
-435 0/10/96lInformation Item Control Room Fire at Palo Verde 1
0.6 435 0/10/96Information item !NRC Strategic Assessment and Rebaselini' 2.3 435 0/10!96. Opening Remarks 0.3 435 0/10/96 P+P Report 0.7 435 0/11/96_Information Item, Human Performance Program Plan 0.2 435 10/11/96 Review Item NRC Thermal Hydraulic Codes i
2 435 0/12/96 Report / Letter NRC Thermal Hydraulic Codes 4.3 435 0/12/96 Report / Letter Adequacy of Code to Analyze SG Tubes 5
435 l 0/12/96 Report / Letter Digital l+C Systems I
5 436 ! 11/7/96; Opening Remarks l
0.3 436 j 11/7/96'Information item Emergency Planning for Advanced Reactor 1.1 436 11/7/96lInformation Item Used of Revised Source Term 0.6 436 11/7/96 Review item Risk-Based Analysis of Reactor Operating 1.2 436 11/7/96 Review item Proposed Rule'on SG Integrity 2.1 436 11/8/96 Reconciliation 0.1 436 11/8/96 Future Activities 0.4 436 11/8/96_Information Item N2 Bubble in Reactor Coolant System 1
436 11/8/96 P+P Report 0.8 436 11/9/96; Report / Letter Annual Report to Congress l
1.5 436 1 11/9/96 Report / Letter Proposed Rule on SG Integrity I
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ACRS MEETINGS 4/1/9 l
Meet Date Activity l
Project Description l Hours 436 11/9/96 Report / Letter Plant-Specific Application of Safety Goals 3.5 436 11/9/96' Report / Letter DSI-22, Future Role of NRC Research 1.5 436 11/9/96l Report / Letter Risk-Based Analysis of Reactor Operating 3.5 437 12/5/96lInformation item Plant Aging Research Program 1.7 437 12/5/96l Review Item Human Performance Program Plan 1.7 437 12/5/96lInformation Item Research program for 1+C Sysrtems 1.5 437 12/5/96l Opening Remarks 0.2 437 12/5/96l Review Item SRP and Reg. Guide for risk-informed, pefr 1.7
)
437 12/6/96; Future Activities 0.6 437 12/6/96lP+P Report 1.1 437 12/6/96lInformation Item NRC Emergency Response Program 1.5 j
437 12/6/96 Reconciliation 0.7 l
437 12/7/96; Report / Letter Human Performance Program Plan 5.8 437 12/7/96 Report / Letter Annual Report to Congress 2
437 12/7/96' Commissioners 2.7 l
l 1
l t1 l
.