|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa ML20138J8241985-12-10010 December 1985 Notification of Licensee Meeting 85-125 on 851213 W/Util in King of Prussia,Pa to Discuss Security Program 1998-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20196J9371998-12-0808 December 1998 Notification of 990120 Meeting with Util in Peekskill,Ny to Inform Public of Licensee Plans for Decommissioning Indian Point Nuclear Generating Station Unit 1 ML20236X5861998-08-0505 August 1998 Summary of 980620 Meeting W/Members of W,Util & NRC in Rockville,Md Re best-estimate Small Break LOCA Model Issues. Attendees List & Nonproprietary Matl Presented at Meeting Encl ML20217E7381997-10-0202 October 1997 Forwards Operator Licensing Exam Administered on 970317-20 W/Outline & Initial Exam Submittal Designated for Distribution Under Rids Code A070 IR 05000247/19970021997-10-0202 October 1997 Forwards NRC Operator Licensing Exam Rept 50-247/97-02 (Including Completed & Graded Tests) for Tests Administered on 970317-20 ML20236N0661997-05-0202 May 1997 Responds to from Consolidated Edison Requesting Interpretation of TS as to Definition of Operable as It Applies to Afs Under Certain Scenarios ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134N6211997-02-19019 February 1997 Forwards Response to SB Bram to EDO Re Proposed Corporate Reorganization of Consolidated Edison Co of Ny Approved W/Edit by Chairman for Dispatch ML20134N6371997-01-14014 January 1997 Requests Concurrence Re Proposed Response to SB Bram to EDO Concerning Proposed Corporate Reorganization of Consolidated Edison Co of Ny by Close of Business on 970117 ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20211E9921995-11-0808 November 1995 Informs of Plan to Augment Plant,Unit 3 Resident Staff & Provide around-the-clock Insp Coverage During Plant Restart from Current Unplanned Outage.Primary Objectives of Insp Listed ML20211D9061995-08-14014 August 1995 Forwards Final Rev to Plant,Unit 3 Restart Action Plan Based Upon Completion of Insp Activities & Util Oversight ML20203B9821995-06-29029 June 1995 Discusses OI Repts 1-95-011,1-95-012 & 5-93-014 Re Fitness for Duty Incident,Falsification of Chemistry Records Involving EDG Fuel Oil & Falsification of Fire Protection Records ML20211F0441994-12-21021 December 1994 Requests That Plant,Unit 3 Restart Action Plan Be Replaced W/Encl Rev to Plan ML20236L5841994-11-0909 November 1994 Submits Interpretation of TS Requirement Re Fire Protection for Indian Point Unit 2 Per 940719 Memo NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20211E9541994-05-12012 May 1994 Requests Approval of Process by Which Plant,Unit 3 Restart Issues,As Listed in Restart Action Plan,Will Be Closed. Restart Issue Closure Process Outlined in Encl to Memo ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057C5721993-09-24024 September 1993 Forwards New Page 20,rev 12 of Security Plan Due to Rev 12 Copy Spillover from Page Nineteen Rev 13 Additions.Page Withheld ML20057B2111993-09-16016 September 1993 Forwards Update to Security Plan,Including Table of Contents,Rev 13 to Pages 18,19,21 & 24 & Chapter 11.Encl Withheld ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant IR 05000286/19900161990-10-25025 October 1990 Notification of Significant Licensee Meeting 90-127/ Enforcement Conference on 901105 in King of Prussia,Pa to Discuss Licensed Reactor Operator Inattentiveness to Duty Noted in Insp Rept 50-286/90-16 ML20059D1341990-08-30030 August 1990 Notification of 900913 Meeting W/Util in Rockville,Md to Discuss Util Proposal to Upgrade Emergency Diesel Generators at Facility ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20196C4751988-06-23023 June 1988 Notification of Licensee Requested Meeting 88-097 on 880629 in King of Prussia,Pa to Discuss Security Program Topics ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195H0201988-02-16016 February 1988 Forwards Proposed Updated SALP Evaluation for Plant. Evaluation Based on Insps & Examiner Reviews Conducted During SALP Period Form 860801-870207 ML20195H0081987-12-0101 December 1987 Forwards Input for SALP Rept for Aug 1986 - Nov 1987 ML20147F8761987-10-21021 October 1987 Discusses 871022 Meeting W/Staff to Discuss NRC Position Re Util Steam Generator Replacement Program.Brief Summary of Licensee Position on Why Replacement Can Be Accomplished Under 10CFR50.59 Listed in Encl 1 ML20204G2771987-03-23023 March 1987 Notification of 870326 Meeting W/Util in Bethesda,Md to Discuss Info Required to Support Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870324 ML20207R2151987-03-10010 March 1987 Notification of 870324 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Facility Decommissioning Plan & Need for Environ Statement.Meeting Originally Scheduled for 870310 ML20212F9321987-03-0303 March 1987 Notification of 870310 Meeting W/Util in Bethesda,Md to Discuss Environ Info Required to Support Decommissioning Plan & Need for Environ Statement ML20211K9161987-02-19019 February 1987 Summary of Operating Reactor Events Meeting 87-04 on 870209. List of Attendees,Events Discussed,Significant Elements of Events & Summary of Events Encl ML20209H0831986-12-22022 December 1986 Summarizes INPO 861210 Accreditation Meeting in Atlanta,Ga. Listed Plants Presented Training Programs for Nonlicensed Operators,Reactor Operators,Senior Reactor Operators & Shift Technical Advisors ML20214T3041986-09-17017 September 1986 Notification of Rev 1 to Board Meeting 86-104 on 860923 at Region I to Discuss Regional Evaluation Phase of SALP ML20203N1921986-09-0808 September 1986 Notification of Board Meeting 86-104 W/Util on 860919 in King of Prussia,Pa to Discuss SALP Regional Evaluation Phase ML20207S2141986-08-0707 August 1986 Forwards Commission Directive to Staff to Respond to Shearon Harris Licensing Board Re Emergency Nighttime Alerting.Staff Should Address Alertability During Stormy Winter in Response to Indian Point Board 860609 & 0710 Ltrs ML20207Q7071986-08-0707 August 1986 Staff Requirements Memo Requesting Provision of point-by- Point Response of Generic Safety Concerns Outlined in ASLB .Response to 860609 & 0710 Requests Re Adequacy of Alert Sys During Stormy Winter Nights Also Requested ML20215A5931986-07-30030 July 1986 Forwards Request for Addl Info on Tech Spec Changes in Response to Generic Ltrs 85-09 & 83-28,Item 4.3 Re Reactor Trip Breaker Design Mods.Request Should Be Transmitted,Along W/Generic Ltr 85-09,to Licensee NUREG/CR-2655, Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 8607111986-07-10010 July 1986 Responds to Bl Brandenburg Re NRC on Facility Alert & Notification Sys.Ltr Info out-of-date But Not Inaccurate.Board Never Informed of NUREG/CR-2655.Served on 860711 ML20198H9381986-05-16016 May 1986 Notifies of 1986 Indian Point 2 full-participation Exercise on 860604 (Insp Rept 50-247/86-13).Team Assignments, Schedule,Exercise Event & Time Line,Open Items,Objective Lists & Synopsis of State & County Matl Encl.W/O Encl ML20199K4421986-05-10010 May 1986 Comments on Indian Point Special Proceeding.Severe Accident Policy Statement Should Be Reexamined ML20198E7621986-05-0808 May 1986 Informs of Next NRR Operating Reactor Events Briefing Scheduled for 850716 in Bethesda,Md.Guidelines for Participants Encl.Tentative Agenda for Meeting Listed ML20214G3971986-05-0808 May 1986 Forwards Sser on Review of Design for Automatic Shunt Trip for Reactor Trip Breakers.Util Response for Seismic Qualification Issue Acceptable.Licensee Will Be Required to Submit Tech Spec Changes ML20198E7981986-05-0808 May 1986 Informs That 850716 NRR Operating Reactor Events Briefing 85-12 Rescheduled for 850723 in Bethesda,Md.Agenda Encl ML20205N1051986-04-24024 April 1986 Requests Assistance in Review of Fuel Handling,Health Physics,Accidents & Environ Areas Per Encl Schedule of Decommissioning Actions ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20140C9931986-01-17017 January 1986 Comments on Proposed Memo Re Draft Annual Rept to EDO Concerning Use of PRA in Insp Program.Memo Fails to Discuss Emergency Risk Projection (Erp) Initiative.Summary of Erp & Probabilistic risk-based Insp Guidance Encl ML20137B3601986-01-0303 January 1986 Notification of SALP Board Meeting 86-006 on 860121 W/Util in King of Prussia,Pa 1998-08-05
[Table view] |
Text
. .
,fas: .
- - ,'t, UNITED STATES "
[ 3.3,f j _ NUCLEAR REGULATORY COMMISSION _
. ?.n..am - v.t.smiNoTot. o. c.2:sss t,.,i' .- '. a;/e i -
- ewe
,, . ~ .
MEMORANDUM FOR: Those on Attached List FROM: David Rubinstein Applied Statistics. Br.anch
. Office 'of Management and Program Analysis
SUBJECT:
A STATISTICMN'S VIEW OF NRC STATISTICS - A PRESENTATION TO THE- ASA ADVISORY COMMITTEE ON NUCLEAR RESEARCH'
~
The encle' sed transcript of'my' talk to the ASA Ad Hoc Cc=mittee,on Nuclear Research might be of interest to you.
- - n *
~-
1 eld.d. ,,, h As.h5A -
David Rubinstein Applied Statistics Branch Office of Ma'nagement and Program Analys.is' En:lesure:
~
As stated . -
cc: See attached list '
~
? ~
. 030505028 8300u4~'
DR ADDCK 05000247 -
PDR -
ENCLOSURE 4
Di r ri: . -4:r.
.. Arra.s:r-H. ~asse:- .
T. Abell R. Sernero W. Bivins .
J. Burns .
M. Cu.1lingford S. Conver . ,
W. Dooly F. Goldstein ,
S. Hanauer J. Griesmeyer (ACRS)
J. Johnson -
R. Hartfield J . Ke r.t L. Lancaster - - ~
I. Kirk
'M. - Messinger '
W. Minner -
- --i S.'Me:1 ewer
- r. v.oisome A. Thtdani -
J. Telford .
L. D. Ong . .
- n. t1.sassion1
.. W. YeselY .
H. Orenstein .
R. Easterling T. Fine R. Me . sing . .
R. M::re O
e we.*
O
. 9e e
A STATZSTICIAN'S VIEW OF'NRC STATISTICS * .
MR. RUBINSTEIN: Since Carl started to talk about where I fit in, let me say that I belong to the Applied Statistics Branch whic,h is the central consulting group on statistical problems, serving all of NRC. We are not part of the risk assessment group, a,nd we have been relatively little involved in risk
. assessment.. Sometimes we get involved either because we push our noses into it and occasionally because we are asked.to. ,
As I was listening to the various speakers. I wanted to change ny speech, b'ut.I' sort of gave up'. I may ' repeat certain things which other speakers l ,
h' ave said. Please forgive me for that.
I should like to start.on an upbeat note. There have been improvements in NRC uses 'of statistics. I seem to sen,se a refre'shing quickening 'of pace; ,
at this meeting and at a meeting last monTth on risk assessment, I noticed -
r .
mdch more concern for the subleties of statistical problems and much more recognition and ackn'owledgment that the past performance has been less, than perfect. This quickening of pace, might be called acceleration ~- I should like to call it "a jerk." In 'ommon c speech a jerk is a sudden
= change in force or acceleration. Engineers us,e the word " jerk", or " jerk .
function" to denote the derivative of acceleration. One might speculate -
that the current large value of the jerk function is caused by anticipation of the judement which you are going to pass. Regardless of the merit of this speculation, the very fact that NRC has invited you to look over its shoulder is an extremely good onen. I am confident that your advice and t
guidance will help to keep the jerk, and perhaps the jerk of the jerk, positive for considerable time to come.
(l.aughter)
A review of statistics at NRC is an ambitious undertaking I cannot do justiceio. It covers a considerable time span; it covers many practitioners -
The latter include. groups at' NRC as,well as practitioners outside of NRC.
working under contract to NRC, as well as employees of vendors and licensees f Often' who are required to demonstrate some aspect of performance or safety.
NRC licensing does rely on analyses . .
perfomed by outsiders. .
I D
'An edited transcript of a talk given by David Rubinstein on Nov. 7,1980 in Washington, D.C., to the ASA (American Statistical Association) Ad Hoc Cormittee
- f. -
_ on__N uclear Reculatory Research. _ _ _ _
Despite the introductory and sincere upbeat note,'here t is still much room for improvement in NRC,'s statistical applications. I shall deal in a broad brush
. fashion with some of the troublesome issues. I want to emphasize the word broad brush; NRC statistics is not a simple monolith. I indicated already evolution over time and that statistics is practiced in one fom or another by many individuals within and outside NRC. Obviously the various individuals and groups do not perfom uniformly well, nor does each perform unifomly well in all instances. ,
Despite diversity of application and quality, some deficiencies can be found rather frequently in statistical applications in the nuclear field. First I shall speculate on why there are rather Trequent shortcomings, and then discuss some of the specific issues, and finally end with some more or less philosophical
' questions. .
~
I believe that the penetration of the AEC and NRC by statisticians ha,s been minimal and rather late, The full subtlety and' complexity of statistical
~
~
problems in the nuclear field ha's not been appreciated by many in the nuclear field, and this includes managerial personnel. There. is widespread belief f- that physical scientis.ts with some acquaintance of stetistical methods can handle statistical problems adequately. This point relates to my next observation. .
- A technological, or perhaps even technocratic attitude, seems rather prevalent in the nuclear field. If there is a problem, there is a technological fix.
- Associated with this attitude or philosophy is an action-oriented approach that is not overly concerned with intellectual considerations; pragmatic considerations will co. Oftentimes, I am concerned whether the methods are even good pragmatism.
The acti,vist approach, whether pragmatically sound or not, is reinforced by pressure to provide answers and to provide them quickly.
l
\ . . .
l r
Before I turn to some of the specific issues, I would like to point out that statistics is at least a moderately successful scien.ce because of somewhat precise concepts and somewhat rigorous methodology. Unfortunately, in the nuclear. field, statistical concepts and methods get often blurred. It is now
.. well known.that th' Lewis e Committee called WASH 1400 inscrutable. ' Leaving WASH 1400 aside, I find much of the statistics in the nuclear field inscrutable.
. or vague. In fact, I -- and I believe other statisticians will -- find some analyses inscrutable, vague, questionable or wrong that might not have been regarded so by the Lewis Comittee.
- ~ .
~
Yesterday, we already noted the confusion of rates, probabilities, and expected values. There were some . incisive coments made about choosing distri-butions for maximum floods, and I would like to note 'that it was an NRC non-i statistician who pointed out that we are frequently concerned with mixtures of populations. .
- Among other items of concern I find: .
- 1. Confusion between ra'ndom variables and parameters is common even when no Bayesian approach is intended. -
- 2. Best estimate is a term that is extremely vague and frefluently used. It could ccme from ' data or from subjective belie'f. It could be a mode, a mean, a median a 50 percent confidence limit -- usually an upper confidence limit -- or what strikes somebody as best without clear elucidation of what is best. It may only be a matter of coincidence that the best estimate is the minimum variance estimate in a particular class of estimates.
- 3. You. Sill often hear the word " uncertainty"; a term that nuclear people seem to be particulary fond of. The first major technical report I reviewed in NRC used the word " uncertainty" where I think the .
2
- following terms might have been more appropriate:
e e
4-a) Random yariable, or perhaps a variation thereof such as random error or measurement error;
.b) Standard deviation; -
c) Confidence Ifmit; d) Error or bias; and perhaps here one could even become more specific whether this was an error in a parameter value or an error in the mathematical model; e) It was also used in that report for the density or distribution
~
function.
At . times I just did "not know what the intended meaning of the word was, and I am not sure that the authors always knew what they were talking about. Other uses and misuses include the following: .
a) The word " uncertainty" is also used as an equivalent to l what is called an upper bound, and this term is not well-defined.
j l
It seems to denote a large or very large value in a not-clearly-specified set of values. In nuclear jargon, " upper bound" is not a literal upper bound. ,
b) Finally, " uncertainty" is used as sort of a catchall phrase for what one might call Bayesian' uncertainties.
c) And, lo and behold, sometimes " uncertainty" is used as the condition of oeing in doubt. This particular usage of the word
- T prefer.
d) R[gardless of the varied nature of the uncertainties, they often are f l ,
sum-root-squared to yield " total uncertainty." k'hile there is frequent l
recognition in the nuclear field of the diversity of uncertainties ~,
~
) ,
much sloppiness and con' fusion still exist.
Now let me turn to some methodological problems. Bay'esian statistics of one
~
sort or another is widely used. The material that 'was distributed to you contains some examples and critiques. I do not wish to elaborate on these in detail. However, even at the . risk of repetition, I should like to point out j that often th'e Bayesian framework is not clearly fonnulated and there is con .
siderable sliding between Bayesian statistics and frequentist statistics, and
, it can go both ways perhaps thiough several cycles in a particular analysis.
Often there is no explicit-mention or an indication of an a priori distribution, and even when a report starts with an a priori distribution, it may not end with
~
an' explicit posteriori distribution or probability. The probabilities seem to h' ave become absolute. _- -
- j. .-
Another technical problem of NRC is' that'5f compon6nts or variance. 'Often we
-] erk'irri.RC with generic values which are evaluated and applied over presumably
'similar classes. Pla'nt to plant variabilities may.be ignored, or differences '
between d'ifferent components may be ignored. The ignored variation may be the dominant contributor to variability arid Bill Vesely in his talk clearly '
recognized this. There has been some progress in dealing with.the complex random
~
structure of the things NRC has worked with, b.ut more systematic exploration, clarification, and proper analysis of the random structure is indicated. .
Model II, or mixed models of the analysis of variance are not well recognized in' NRC. For that matter, Model I may be ignored.
As Bill Vesely pointed out, human factors and common cause problems are important, or perhaps even dominant contributors, to risk. It is extremely difficult to model these convincingly and to find appropriate data for ' estimation of parameters.
' ~
'In NRC terminology, there are great uncertainties with respect to these areas.
This ' leads to some philosophical questions.
In view of large and not necessarily well understood uncertainties, can one properly qua,ntify uncertainties? How should numerical analyses be used? How
- should they'be comunicated? The subject of comunication is a large one in / ,
itself. . - -
l ._ ._. . . -. . -
A related 'ouestion is what should be the proper role of subjective judgment in go'vernmental policy and regulation and how should one deal with subjective judgments and how should they be presented to the public and the political' representatives? ~
I was going to stop here, but Mike Cullingford stimulated me to say that perhaps we.shouldn't argue about whether we want Bayesian statistics or classical statistics. Perhaps we should ask the question, what is good scientific inference? -
Thank you.
W 4
es l
t'-
I i !
e me
, s -
^ O *
. e _ _._.._,.