LD-95-026, Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER
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| ML20093B271 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 10/06/1995 |
| From: | Brinkman C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ASEA BROWN BOVERI, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LD-95-026, LD-95-26, NUDOCS 9510110309 | |
| Download: ML20093B271 (2) | |
Similar Documents at 05200002 | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20249C1601998-06-24024 June 1998
[Table view]Transmits Revised Fda for Sys 80+ Design,Per App O of 10CFR52.Duration of Fda Conforms W/Duration of Design Certification Rule for Sys 80+ Std Design LD-98-009, Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info1998-03-13013 March 1998 Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. 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All CESSAR-DC Pages Designated Except for Listed Info1998-03-13013 March 1998
[Table view]Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization LD-97-020, Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl1997-06-13013 June 1997 Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl LD-97-015, Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 19971997-05-0707 May 1997 Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 1997 LD-97-014, Transmits Final Version of Sys 80+ Design Control Document (DCD)1997-04-30030 April 1997 Transmits Final Version of Sys 80+ Design Control Document (DCD) LD-96-062, Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication1996-12-18018 December 1996 Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication LD-96-060, Forwards Rev to Sys 80+ Std Plant Design Control Document1996-12-13013 December 1996 Forwards Rev to Sys 80+ Std Plant Design Control Document LD-96-042, Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed1996-09-26026 September 1996 Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking LD-96-029, Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking1996-07-25025 July 1996 Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking LD-96-028, Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages1996-07-17017 July 1996 Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages LD-96-024, Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document1996-06-27027 June 1996 Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document LD-96-021, Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval1996-06-11011 June 1996 Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval ML20107G1451996-04-17017 April 1996 Transmits CEOG Task 931 Survey Questionnaire-CEA Insertion Experience W/High Burnup Fuel Mgt ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations LD-95-026, Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER1995-10-0606 October 1995 Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER LD-95-040, Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package1995-09-0505 September 1995 Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package ML20092D2561995-08-23023 August 1995 Forwards Correction to Comment 20 Re Proposed Design Certification Rules for Standardized Advancement Reactors. Last Line of Text May Have Been Lost Due to Word Processing Error ML20092D2871995-08-23023 August 1995 Forwards Correction to Comment 19 Re Proposed Design Certification Rules for Standardized Advanced Reactors. 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Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page1995-03-17017 March 1995 Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page LD-95-003, Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document1995-03-0303 March 1995 Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document LD-95-007, Forwards Revised Sys 80+ Design Control Document1995-02-22022 February 1995 Forwards Revised Sys 80+ Design Control Document LD-95-006, Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc1995-02-16016 February 1995 Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc LD-95-001, Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design1995-01-0606 January 1995 Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design NRC-94-4383, Comments on Review of Draft NUREG-1512 for Proprietary Info1994-12-27027 December 1994 Comments on Review of Draft NUREG-1512 for Proprietary Info LD-94-072, Provides Justification for Tier 2 Seismic & Valve Testing Expirations1994-12-16016 December 1994 Provides Justification for Tier 2 Seismic & Valve Testing Expirations LD-94-073, Forwards Sys 80+ Design Control Document, Vols 1-241994-12-16016 December 1994 Forwards Sys 80+ Design Control Document, Vols 1-24 LD-94-071, Transmits Addl Input to System 80+ Design Control Document1994-12-15015 December 1994 Transmits Addl Input to System 80+ Design Control Document LD-94-069, Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers1994-12-0808 December 1994 Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers ML20078N8961994-12-0101 December 1994 Forwards Copy of Ltr NFBWR-94-033 LD-94-065, Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule1994-10-28028 October 1994 Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule LD-94-063, Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design1994-10-10010 October 1994 Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design ML20072T2691994-08-30030 August 1994 Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+ LD-94-059, Forwards Draft Notice of Issuance of EA & Draft Fonsi, Together W/Supporting Draft Proposed EA for Consideration,W/ Respect to Draft EA NRC Producing for Proposed Sys 80+ Design Process1994-08-22022 August 1994 Forwards Draft Notice of Issuance of EA & Draft Fonsi, Together W/Supporting Draft Proposed EA for Consideration,W/ Respect to Draft EA NRC Producing for Proposed Sys 80+ Design Process ML20072B9641994-08-12012 August 1994 Requests That Author Name Be Added to Sys 80+ Service List. Author Counsel to Westinghouse in AP600 Design Certification ML20072E3561994-08-0909 August 1994 Requests Addition of Author Name to Sys 80+ Svc List ML20073E1721994-07-25025 July 1994 Forwards Rept Entitled, Analysis of Ex-Vessel Steam Explosions for Combustion Engineering Sys 80+ Using Gtsf Computer Code. Provides Comments on Central,Outer & Multiple Instrument Tube Failures LD-94-054, Forwards Errata to Sys 80+ Certified Design Matl,In Response to Editorial & Word Processing Errors1994-07-21021 July 1994 Forwards Errata to Sys 80+ Certified Design Matl,In Response to Editorial & Word Processing Errors LD-94-052, Requests That Service List for Docket 52-002 Be Updated in Accordance W/Encl Listing,Due to Changes in Position Titles, Affiliations & Organizations.Correspondence on Docket 52-002 Should Be Addressed to Listed Address1994-07-20020 July 1994 Requests That Service List for Docket 52-002 Be Updated in Accordance W/Encl Listing,Due to Changes in Position Titles, Affiliations & Organizations.Correspondence on Docket 52-002 Should Be Addressed to Listed Address LD-94-053, Seeks Confirmation of Vendor Understanding of NRC Fee Regulations in 10CFR170 as Pertaining to Sys 80+ Design Certification Rulemaking as Set Forth in Encl1994-07-20020 July 1994 Seeks Confirmation of Vendor Understanding of NRC Fee Regulations in 10CFR170 as Pertaining to Sys 80+ Design Certification Rulemaking as Set Forth in Encl LD-94-048, Forwards Certified Design Matl Related to Design Reliability Assurance Program & Corresponding Errata Pages for CESSAR-DC (Section 1.0,17.3 & 19.15) Amend W,To Resolve NRC Comments Received by Telcon Over Past Two Wks1994-07-12012 July 1994 Forwards Certified Design Matl Related to Design Reliability Assurance Program & Corresponding Errata Pages for CESSAR-DC (Section 1.0,17.3 & 19.15) Amend W,To Resolve NRC Comments Received by Telcon Over Past Two Wks ML20077F4111994-07-0808 July 1994 Forwards Technical Evaluation Rept Entitled, an Analysis of Core Meltdown Accidents in CE Sys 80+ Plant Using Melcor LD-94-047, Forwards Replacement Page for System 80+ Emergency Operations Guidelines1994-06-28028 June 1994 Forwards Replacement Page for System 80+ Emergency Operations Guidelines LD-94-046, Submits Sys 80+ Design & Operational Features Re Deviations from Regulations1994-06-27027 June 1994 Submits Sys 80+ Design & Operational Features Re Deviations from Regulations LD-94-044, Forwards Revised Combustion Engineering Standard Safety Analysis Rept - Design Certification,Amend W & Affidavit1994-06-20020 June 1994 Forwards Revised Combustion Engineering Standard Safety Analysis Rept - Design Certification,Amend W & Affidavit 1998-03-13 |
Text
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a .
A BB 4 NO October 6,1995 B
LD-95-026 Docket 52-002 Attn: Document Control Desk
' U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
~ System 80+" Probabilistic Risk Assessment
Dear Sirs:
The System 80+ Final Safety Evaluation Report (FSER) has been widely distributed in the U.S. and abroad. This FSER has been well received and feedback has demonstrated that the FSER is a detailed document that authoritatively addresses safety issues. However, one item in the Probabilistic Risk Assessment (PRA) has been significantly mis-interpreted, and ABB-CE, therefore, requests that the NRC provide an additional explanation of the PRA results.
This request is only for clarification and does not impact the conclusions of the evaluation already reported in the FSER.
The System 80+ base case core damage frequency (CDF) assumes reactor vessel failures are oflow-probability, but credible, and that common cause failures are also credible. These base case results have been misused by comparing them to PRA results reported to NRC by other designers that assume reactor vessel and common cause failures are incredible. Section 19.10.10 of CESSAR-DC describes System 80+ CDF sensitivity to assumptions on reactor vessel rupture and common cause failures. System 80+ results, assuming that reactor vessel and common cause failures are incredible, are presented in Table 19.10-1, item 10C.
To avoid future misrepresentation, it would be most helpful ifNRC staffissued a letter and/or FSER supplement stating that, based on the sensitivity results presented in Table 19.10-1 item IOC, the System 80+ CDF is reduced from 1.67E-06 events / year to 1.41E-07 events / year. In addition, it may be appropriate to alert readers that comparisons ofPRA results, if done at all, require careful review to ensure that equivalent assumptions are used.
100036 ABB Combustion Engineering Nuclear Systems Cg ist=-
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j combusbon Engineenr4 Inc. 1000 Prospt:ct Hdt Road Telephone (203) 688-1911 k ji a Jrf .,
PO Box 500 Fax (203) 285-5203 "5'.cT w m -
9510110309 951006 PDR ADOCK 05200002 C PDR
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Please call me or Mr. Stan Ritterbusch at 203-285-5206 ifyou have any questions.
Very truly yours, COMBUSTION ENGINEERING, INC.
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. C _ w/ -s C. B. Brinkman Director Nuclear Systems Licensing cc: S. Magruder (NRC)
N. Fletcher (DOE) l l
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