Comments on Draft Ltr from Hanauer to Cooper on Nuppsco Committee.Ltr Acceptable,However,Info Re Safety Classification/Terminology Issue Requires Further Discussion to Standardize Term DefinitionsML20151H775 |
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Indian Point |
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Issue date: |
03/18/1982 |
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From: |
Conran J NRC |
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To: |
Coffman F NRC |
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Shared Package |
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ML20151H308 |
List: |
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References |
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NUDOCS 8305050295 |
Download: ML20151H775 (5) |
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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] |
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NOTE TO: Frank Coffman FROM: Jim Conran -
SUBJECT:
COMMENTS ON DRAFT LETTER (HANAUER TO COOPER-NUPPSCO)...AND
. RELATED MATTERS.
The Draft letter looks ok to me as is; but c bit more should be said about the pot that is boiling here. I have talked to Carl Johnson, RES (NRC's representa-tive on the NUPPSCO Committee referred to in the incoming) regarding the safety classification /terininology issue in'volved here. He sent to me the draft of NUPPSCO's proposed " alternative definitions" (see attached) plus a Minority Report reflecting the views of dissenting members of the NUPPSCO Committee (also attached).
. My comments to him regarding these matters were:
(a) The proposed definitions gy, be consistent (as claimed) with Denton's
" standard definitions" (approved by Denton on 11/20/81 - seeattached);
but it would surely involve a very substantial review effort to-demonstrate / prove that point. And even if that were done, in my opinion.
we would not have " gained" anything; we would only then have additional, new safety classification tems which we would then have to try to get everybody to learn and Ose consistently.
(b) We really don't need any ,new (alternatiye) safety classificatiori terms defined; we just need standardization (consistency), within both the staff and the industry, in the usage of the tems already included in the regulations and existing regulatory guidance document (e.g. Reg. .
Guides , SRPs, NUREGs , etc.). That was the purpose of Denton's 11/20/81 memo to all NRR
- people. The need to take the next obvious step .
(i.e. incorporating Denton's standard definitions into the "0EFINITIONS" sections of the regulations so that staff and industry must/can use them consistently) is readily apparent from .the NUPPSCO dissenter's usage of the term "Important to Safety" in the Minority Report.
i (c) Although I am not, and we (NRR) should not , be, receptive to the proposed new " alternative" safety classification language, the underlying or associated industry effort to understand the relative safety importance of reactor plant components, and to establish a basis for sorting those components into various categories, should be of great interest to us.
I think Hanauer is right in wanting to talk with industry about their approach, categorization bases, etc. This more interesting andepoten-tially useful aspect of the industry effort in. developing the new pFoposed standards ANS 51.1 and ANS 52.1, is apparently spelled out in considerable detail in those draft standards; so I have asked Carl to obtain and send to us copies of them prior to the (rescheduled) Hanauer.-e meeting with NUPPSCO members. That kind of info is clearly related toi i
p O 7 PDR ENCLOSURE 6
F. Coffman
and would probably be valuable input to a number of RES and NRR 3 "importance ranking" type efforts already underway (e.g. A-1291 (RRAB);
A-1295 (RRAB); Walt Haass' Graded Q.A. Development effort just getting underway with EGG as contractor; RES long-term importance ranking / graded Q.A. effort just getting underway with Sandia as contractor; etc.).
2 Our (RRAB and DST) proper course for the future regarding this general topic should be to propose that Denton's " standard definitions" be formally incorporated into '
the appropriate " DEFINITIONS" section of the regulations (e.g.10 CFR 50 Appendix A 4 and Appendix B, and 10 CFR 100 Appendix A). This would clarify to the public and the industry (as well as to the entire NRC staff) that we (NRC) know what our regulations and regulatory guidance mean , and that we intend to enforce consistent interpretation and application of them. At the same time, we must be sensitive to the industry's concern (as reflected in the Nt!PPSCO Minority Report) that by clarifying and insisting on consistent usage of the language of our regulations, we are " changing the meaning" of that language (e.g. important to safety) in order to sneakily ratchet or broaden the scope of the existing regulations. For that reason, the same language Denton used in his 11/20/81 letter to ALL NRR to emphasize that point should be included in the " Discussion" section of the Proposed Rule that would incorporate his " standard definitions" as I have suggested.
To really wrap this thing up right, we should also initiate the development of another Reg. Guide and another SRP section to, provide further detail / discussion /
( ., guidance to both the staff and the industry regarding , proper application of Denton's " standard definitions." I know that Thadani and Ernst have been somewhat reltictant to involve us heavily'in this kind of actiIvity in the past because of our severely limited resources;' but the passage of time has indicated clearly, I believe, that if we (who happen to know best the " background" of the development of Denton's " standard definitions") don't take the initie'tive in getting done what I am recommending, it simply isn't going to get done. And, as you know, a great deal of support has developed for getting it done (e.g. from ELD,.RES, ACRS, and ASLB, TMI-l Board) as a result of our having addressed these issues in a number of different contexts over the past 1 years. This is not just " word smithing";
what is involved is the precise meaning of the specific language that describes some of the nost fundamental concepts of our regulatory structure and philosophy.
We really ought to get it (consistently) right, sometime soon.
l cd: J.Conran Chron 9
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EXCERPT FROM REBUTTAL TESTIMONY ON CONTENTION 7B, DATED 7/1/82, BY. J. H. CONRAN TO THE SHOREHAM ASLB O
A. The Staff does not believe it is acceptable for the language differences indicated in the statements on p. 55 of Applicant's testimony to go unresolved because of certain unacceptable implications of the different usage of the safety classification language of the regulations.
These implications obtain not only with regard to Shoreham licensing but
] also with regard to the efficacy of the Staff's approach and methods of safety review in more general application. .There are at least three such i
implications: ,
, l '. Because the Staff conducts an audit review, reliance must be placed on commitments by Applicants that all portions of the regulations are complied with (see, e.g., FSAR 5 3.1.2.1). It is critical that these commitments mean what the Staff understands'them to mean if the Staff's determination of " reasonable assurance" (which finding must be made in accordanr.e with 10 C.F.R. 5 50.35(c) in order to license a facility) is to be. meaningful in the sense intended in the regulations.
. 2. It is clear under the Staff's understanding of "important to ,.
safety" _(but not under Applicant's) that there exists in the regulations a requirement under GDC 1 for a QA program for certain non-safety-related structures, systems and components (i.e., those important to safety). .-
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ENCLOSURE 7
7-
- 3. Under Applicant's construction of "important to safety," the ,
obligations imposed by 10 C.F.R. Part 21 might be more narrowly construed
, than would be the' c'ase under the Staff's broader definition of .that term.
~
These examples demonstrate why agreement on the safety classification definitions provided by the Denton definition is extremely significant.
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