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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20129C3241996-10-21021 October 1996 Forwards Response to NEI Proposals Re Three Design Certification Issues 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 ML20149E5221994-06-0909 June 1994 Requests Commission Approval to Publish Encl FSER for GE ABWR Design Indicated in 940304 Memo ML20149E5131994-05-31031 May 1994 Informs That NRC in Process of Completing FSERs for Both GE Advanced BWR & ABB-CE Sys 80+ Designs.Safety Conclusions Will Need to Be Reassessed by Both NRC & Design Certification Applicants on Listed Issues ML20059E4941994-01-0707 January 1994 Submits to file,931230 Ltr to J Quirk,Ge Nuclear Energy, W/Copy of FSER on ABWR Design ML20058G9931993-12-0101 December 1993 Notification of 931214 Meeting W/Us Dept of Energy in Rockville,Md to Discuss Status of Advanced Reactor Reviews. Agenda Encl ML20058B0441993-11-15015 November 1993 Forwards Advanced Copy of Draft Paper, Diversity in Method of Measuring RPV Level in ABWR & Sbwr, to Keep Commission Informed About Key Policy & Technical Issues Bearing on Future LWR Designs ML20059K2761993-11-0101 November 1993 Notification of 931110-11 Meeting W/Ge in San Jose,Ca to Discuss Info to Be Included in Nov Submittal of Ssar & Design Certification Material for ABWR Design ML20059J2581993-10-29029 October 1993 Requests Addl Info to Complete Review of Chapter 12 of GE Sbwr Ssar ML20059K3201993-10-26026 October 1993 Advises That Commission Has Agreed W/Staff Recommendation That GE Be Required to Prepare ABWR Design Control Document in SI & Provide Conversion Table from SI to English Units in Lieu of Providing Dual Units ML20057C5411993-09-23023 September 1993 Notification of 930928-30 Meeting W/Ge Nuclear Energy in San Jose,Ca to Discuss Status of Development of TS for Advanced Boiling Water Reactor (ABWR) ML20057B9491993-09-20020 September 1993 Notification of 930921 Meeting W/Ge Nuclear Energy in San Jose,Ca to Discuss ABWR Fire Protection Issues ML20057B6031993-09-16016 September 1993 Notification of Meeting W/Ge on 931014 in Rockville,Md to Discuss Remaining Design Re Open Issues for ABWR ML20057E9411993-09-16016 September 1993 Revised Notification of 931014 Meeting W/Ge in Rockville,Md to Discuss Remaining Design Related Open Issues for Abwr. Time Changed from 11:30 Pm to 4:30 Pm ML20057A8161993-09-0909 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Probabilistic Risk Assessment,Severe Accident,Ts, Unresolved Safety Issues/Generic Safety Issues & Reactor Sys ML20057B4381993-09-0909 September 1993 Informs of Cancellation of 930928 Meeting W/Ge in Rockville,Md ML20056H6471993-09-0707 September 1993 Notification of 930908 & 09 Meetings W/Ge in Rockville,Md to Discuss Resolution of USIs & GSIs for ABWR Design ML20056E0931993-08-17017 August 1993 Notification of 930819 & 20 Meeting W/Ge in Rockville,Md to Discuss Status of Development of TSs for ABWR ML20057D1151993-08-16016 August 1993 Notification of 931005 Meeting w/DOE,ABB-CE & GE in Rockville,Md to Discuss Design Certification Reviews. Meeting Cancelled ML20056E0921993-08-16016 August 1993 Notification of 931005 Mgt Meeting W/Doe in Rockville,Md to Discuss Status of Design Certification Reviews ML20056D9391993-07-30030 July 1993 Notification of 930823-26 Meeting W/Ge to Discuss Instrumentation & Control TS for ABWR ML20056D0671993-07-19019 July 1993 Submits Daily Highlights Re Meeting W/Ge in San Jose,Ca to Discuss ITAAC for ABWR ML20128K2761993-02-12012 February 1993 Notification of 930203-25 Meeting W/Ge in San Jose,Ca to Discuss Open Items Identified by Staff Review of Chapter 8 (Electrical Sys) of Ssar for ABWR ML20128H0421993-02-0909 February 1993 Forwards Proprietary Rev 0 to PED-18-0389, PECO Peach Bottom 2 & 3 Nuclear Power Plants...Mg Set Missile Generation Study, for Use in Review of ABWR Ssar.Encl Withheld ML20128G2601993-02-0909 February 1993 Discusses Ways to Expedite Review of Design Certification Application for ABWR & Lists Scenarios for ACRS Review within One Month Review Period ML20128C2081993-01-29029 January 1993 Notification of 930203-04 Meeting W/Ge in Rockville,Md to Discuss Guidelines for ITAAC for ABWR ML20127P4701993-01-26026 January 1993 Notification of 930222 & 23-25 Meeting W/Ge in San Francisco,Ca to Conduct Design Calculation Audit & to Close Out Open Items Identified in Dser ML20127H0531993-01-15015 January 1993 Notification of 930125 Meeting W/Ge in San Jose,Ca to Discuss & Resolve Outstanding Open,Confirmatory & Insps, Tests,Analyses & Acceptance Criteria Items in Draft Final Ser,Chapters 2,6, & 15 ML20127F6441993-01-11011 January 1993 Notification of 930120 Meeting W/Ge in San Jose,Ca to Discuss ABWR Draft Final SER Open Items Re PRA ML20127C0401993-01-0808 January 1993 Notification of 930121 Meeting W/Ge in San Jose,Ca to Discuss ABWR Open Items & Staff Review Schedule ML20127B5401993-01-0707 January 1993 Notification of 930108 Meeting W/Ge in Rockville,Md to Discuss ABWR Open Issues ML20127D6651992-12-29029 December 1992 Forwards Fax Sent to J Duncan of GE Providing Updated Punch List for Advanced BWR PRA Issues ML20127C7991992-12-28028 December 1992 Forwards Fax Sent to J Duncan,Requesting Clarification of GE Submittal on PRA Input to Reliability Assurance Program ML20126F5671992-12-22022 December 1992 Notification of 930111-14 Meeting W/Ge in San Jose,Ca to Discuss Insps,Tests,Analyses & Acceptance Criteria for GE Advanced BWR ML20127D6431992-12-22022 December 1992 Forwards Fax to J Duncan of GE Re Areas Needed to Provide Clarification of Draft Ssar Submittal on LOCA Outside Containment ML20126C0921992-12-11011 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Insp,Tests & Analyses for GE ABWR ML20125A4131992-12-0303 December 1992 Notification of 921208-10 Meeting W/Licensee in San Jose,Ca to Discuss Open Items Identified by Staff Review of Chapters 3,6,9,10 & 11 of Ssar for ABWR ML20127P5811992-12-0101 December 1992 Forwards 45 ABWR Drawings Re Intersys LOCA Issue.Drawings Received During 921029 Meeting W/Ge ML20127C6671992-12-0101 December 1992 Forwards Fax Sent to J Duncan,Ge That Updates Status of Advanced BWR PRA Issues ML20198E3061992-11-19019 November 1992 Summarizes 921110 NRC-NUMARC Meeting in Rockville,Md,To Discuss first-of-a-kind Engineering Planned for Alwr Plants ML20127C8041992-11-16016 November 1992 Forwards Corrected Guidance on Performance of PRA-based Seismic Margins Analysis NUREG-1469, Submits Advanced Comments for Meeting of ABWR GE & ACRS Re NUREG-14691992-11-10010 November 1992 Submits Advanced Comments for Meeting of ABWR GE & ACRS Re NUREG-1469 ML20114A0451992-08-0404 August 1992 Forwards Amend 21 Reprinted Pages to Correct Disconnects/ Discrepancies Mailed in Earlier Transmittal ML20099A9331992-07-22022 July 1992 Forwards Amend 21 Reprinted Pages to Correct Disconnects/ Discrepancies in Earlier Transmittal ML20099B3971992-07-22022 July 1992 Forwards Proprietary Amend 21 Reprinted Pages to Correct Disconnects/Discrepancies in Earlier Transmittal.Encl Withheld ML20098D2991992-05-21021 May 1992 Forwards Draft Summary of Advanced BWR Level 1 PRA Updated Results to Be Transmitted to NRC Including,Tabular Breakdown of Core Damage Frequency by Initiating Event & Accident Class ML20101L0001992-05-0808 May 1992 Forwards Proprietary Drafts Re Updated Advanced BWR Std Plant.Encl Withheld ML20101H2431992-05-0707 May 1992 Forwards Draft Tables 19Q.4-1, ABWR Features That Minimize Shutdown Risk & 19QB-2, ABWR Features to Prevent/Mitigate Loss of DHR Precursor Events. Submittal of Table Satisfies Draft SER Item 0-20 Subtasks 1 & 2.Tables Withheld ML20071L3691989-04-0505 April 1989 Advises That Secy 88-248 Will Be Superseded by New Commission Paper on GE Advanced BWR to Be Provided for Review on 890505 1996-10-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20129C3241996-10-21021 October 1996 Forwards Response to NEI Proposals Re Three Design Certification Issues 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 ML20149E5221994-06-0909 June 1994 Requests Commission Approval to Publish Encl FSER for GE ABWR Design Indicated in 940304 Memo ML20149E5131994-05-31031 May 1994 Informs That NRC in Process of Completing FSERs for Both GE Advanced BWR & ABB-CE Sys 80+ Designs.Safety Conclusions Will Need to Be Reassessed by Both NRC & Design Certification Applicants on Listed Issues ML20059E4941994-01-0707 January 1994 Submits to file,931230 Ltr to J Quirk,Ge Nuclear Energy, W/Copy of FSER on ABWR Design ML20058G9931993-12-0101 December 1993 Notification of 931214 Meeting W/Us Dept of Energy in Rockville,Md to Discuss Status of Advanced Reactor Reviews. Agenda Encl ML20058B0441993-11-15015 November 1993 Forwards Advanced Copy of Draft Paper, Diversity in Method of Measuring RPV Level in ABWR & Sbwr, to Keep Commission Informed About Key Policy & Technical Issues Bearing on Future LWR Designs ML20059K2761993-11-0101 November 1993 Notification of 931110-11 Meeting W/Ge in San Jose,Ca to Discuss Info to Be Included in Nov Submittal of Ssar & Design Certification Material for ABWR Design ML20059J2581993-10-29029 October 1993 Requests Addl Info to Complete Review of Chapter 12 of GE Sbwr Ssar ML20059K3201993-10-26026 October 1993 Advises That Commission Has Agreed W/Staff Recommendation That GE Be Required to Prepare ABWR Design Control Document in SI & Provide Conversion Table from SI to English Units in Lieu of Providing Dual Units ML20057C5411993-09-23023 September 1993 Notification of 930928-30 Meeting W/Ge Nuclear Energy in San Jose,Ca to Discuss Status of Development of TS for Advanced Boiling Water Reactor (ABWR) ML20057B9491993-09-20020 September 1993 Notification of 930921 Meeting W/Ge Nuclear Energy in San Jose,Ca to Discuss ABWR Fire Protection Issues ML20057B6031993-09-16016 September 1993 Notification of Meeting W/Ge on 931014 in Rockville,Md to Discuss Remaining Design Re Open Issues for ABWR ML20057E9411993-09-16016 September 1993 Revised Notification of 931014 Meeting W/Ge in Rockville,Md to Discuss Remaining Design Related Open Issues for Abwr. Time Changed from 11:30 Pm to 4:30 Pm ML20057A8161993-09-0909 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Probabilistic Risk Assessment,Severe Accident,Ts, Unresolved Safety Issues/Generic Safety Issues & Reactor Sys ML20057B4381993-09-0909 September 1993 Informs of Cancellation of 930928 Meeting W/Ge in Rockville,Md ML20056H6471993-09-0707 September 1993 Notification of 930908 & 09 Meetings W/Ge in Rockville,Md to Discuss Resolution of USIs & GSIs for ABWR Design ML20056E0931993-08-17017 August 1993 Notification of 930819 & 20 Meeting W/Ge in Rockville,Md to Discuss Status of Development of TSs for ABWR ML20057D1151993-08-16016 August 1993 Notification of 931005 Meeting w/DOE,ABB-CE & GE in Rockville,Md to Discuss Design Certification Reviews. Meeting Cancelled ML20056E0921993-08-16016 August 1993 Notification of 931005 Mgt Meeting W/Doe in Rockville,Md to Discuss Status of Design Certification Reviews ML20056D9391993-07-30030 July 1993 Notification of 930823-26 Meeting W/Ge to Discuss Instrumentation & Control TS for ABWR ML20056D0671993-07-19019 July 1993 Submits Daily Highlights Re Meeting W/Ge in San Jose,Ca to Discuss ITAAC for ABWR ML20128K2761993-02-12012 February 1993 Notification of 930203-25 Meeting W/Ge in San Jose,Ca to Discuss Open Items Identified by Staff Review of Chapter 8 (Electrical Sys) of Ssar for ABWR ML20128H0421993-02-0909 February 1993 Forwards Proprietary Rev 0 to PED-18-0389, PECO Peach Bottom 2 & 3 Nuclear Power Plants...Mg Set Missile Generation Study, for Use in Review of ABWR Ssar.Encl Withheld ML20128G2601993-02-0909 February 1993 Discusses Ways to Expedite Review of Design Certification Application for ABWR & Lists Scenarios for ACRS Review within One Month Review Period ML20128C2081993-01-29029 January 1993 Notification of 930203-04 Meeting W/Ge in Rockville,Md to Discuss Guidelines for ITAAC for ABWR ML20127P4701993-01-26026 January 1993 Notification of 930222 & 23-25 Meeting W/Ge in San Francisco,Ca to Conduct Design Calculation Audit & to Close Out Open Items Identified in Dser ML20127H0531993-01-15015 January 1993 Notification of 930125 Meeting W/Ge in San Jose,Ca to Discuss & Resolve Outstanding Open,Confirmatory & Insps, Tests,Analyses & Acceptance Criteria Items in Draft Final Ser,Chapters 2,6, & 15 ML20127F6441993-01-11011 January 1993 Notification of 930120 Meeting W/Ge in San Jose,Ca to Discuss ABWR Draft Final SER Open Items Re PRA ML20127C0401993-01-0808 January 1993 Notification of 930121 Meeting W/Ge in San Jose,Ca to Discuss ABWR Open Items & Staff Review Schedule ML20127B5401993-01-0707 January 1993 Notification of 930108 Meeting W/Ge in Rockville,Md to Discuss ABWR Open Issues ML20127D6651992-12-29029 December 1992 Forwards Fax Sent to J Duncan of GE Providing Updated Punch List for Advanced BWR PRA Issues ML20127C7991992-12-28028 December 1992 Forwards Fax Sent to J Duncan,Requesting Clarification of GE Submittal on PRA Input to Reliability Assurance Program ML20126F5671992-12-22022 December 1992 Notification of 930111-14 Meeting W/Ge in San Jose,Ca to Discuss Insps,Tests,Analyses & Acceptance Criteria for GE Advanced BWR ML20127D6431992-12-22022 December 1992 Forwards Fax to J Duncan of GE Re Areas Needed to Provide Clarification of Draft Ssar Submittal on LOCA Outside Containment ML20126C0921992-12-11011 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Insp,Tests & Analyses for GE ABWR ML20125A4131992-12-0303 December 1992 Notification of 921208-10 Meeting W/Licensee in San Jose,Ca to Discuss Open Items Identified by Staff Review of Chapters 3,6,9,10 & 11 of Ssar for ABWR ML20127P5811992-12-0101 December 1992 Forwards 45 ABWR Drawings Re Intersys LOCA Issue.Drawings Received During 921029 Meeting W/Ge ML20127C6671992-12-0101 December 1992 Forwards Fax Sent to J Duncan,Ge That Updates Status of Advanced BWR PRA Issues ML20198E3061992-11-19019 November 1992 Summarizes 921110 NRC-NUMARC Meeting in Rockville,Md,To Discuss first-of-a-kind Engineering Planned for Alwr Plants ML20127C8041992-11-16016 November 1992 Forwards Corrected Guidance on Performance of PRA-based Seismic Margins Analysis NUREG-1469, Submits Advanced Comments for Meeting of ABWR GE & ACRS Re NUREG-14691992-11-10010 November 1992 Submits Advanced Comments for Meeting of ABWR GE & ACRS Re NUREG-1469 ML20114A0451992-08-0404 August 1992 Forwards Amend 21 Reprinted Pages to Correct Disconnects/ Discrepancies Mailed in Earlier Transmittal ML20099A9331992-07-22022 July 1992 Forwards Amend 21 Reprinted Pages to Correct Disconnects/ Discrepancies in Earlier Transmittal ML20099B3971992-07-22022 July 1992 Forwards Proprietary Amend 21 Reprinted Pages to Correct Disconnects/Discrepancies in Earlier Transmittal.Encl Withheld ML20098D2991992-05-21021 May 1992 Forwards Draft Summary of Advanced BWR Level 1 PRA Updated Results to Be Transmitted to NRC Including,Tabular Breakdown of Core Damage Frequency by Initiating Event & Accident Class ML20101L0001992-05-0808 May 1992 Forwards Proprietary Drafts Re Updated Advanced BWR Std Plant.Encl Withheld ML20101H2431992-05-0707 May 1992 Forwards Draft Tables 19Q.4-1, ABWR Features That Minimize Shutdown Risk & 19QB-2, ABWR Features to Prevent/Mitigate Loss of DHR Precursor Events. Submittal of Table Satisfies Draft SER Item 0-20 Subtasks 1 & 2.Tables Withheld ML20071L3691989-04-0505 April 1989 Advises That Secy 88-248 Will Be Superseded by New Commission Paper on GE Advanced BWR to Be Provided for Review on 890505 1996-10-21
[Table view] |
Text
, .
. 3be kd sa- 00, -
December 1, 1992 liOTE TO: C(et[Poslusn///,NRR-
/.
FROM: G,lefgMy W DSSA, liRR SUBJECl: FAX FROM GE/ FAX 10 GE i
I have enclosed a fax 1-sent to Jack Duncan, GE that updates the status.of ABWR PRA issues. 1 aTso nove coulus h -fur sent-te T.c by Jack-Duncan-o+s LAC 4&-tmWtttemf cDD t u i w;+n t .
Enclosure \: as stated -
4 e
a 130011 l o L' ;
. 9301140291 921201 -
/f PDR ADDCK 052OOOO1- -
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T The following chart is a summary of the status of issues raised by the staff
' - concerning the ABWR PRA. This chart has been coordinated with GE to assure that it is as accurate as possible in portraying issue status. The chart is current as of November 30, 1992.
An issue is judged " confirmatory" in the chart if GE has submitted (by fax, discussion, meeting handout, or letter) sufficient information for the staff to draw its conclusion regarding the issue.- Most of the information submitted by GE has been provided in a preliminary form. All information must be translated by GE into SSAR modifications that capture issuc resolution.
An issue is judged to be "open" in the chart if the staff is awaiting GE's response on staff questions or if the staff still has the issue under review.
4 2
- l. '.
a
SIALUS OF_ABWR_B A_ ISSUES November 30, 1992 IS.5MLD151RifilpN .11MllS_ ACIJ.ON G0NE21LtiMPRY I$ SUES
- 1. RPS Reliability 0-1
- 2. GE to update ECCS FT-1A - IB and other fault trees
- 3. GE to defend 10RV S-2 frequency
- 4. GE to defend 10RV C-1 success criteria
- 5. GE to defend one S-1 unplanned trip per year
- 6. GE to evaluate 0-2 support system failures as initiating events
- 7. GE to confirm LOSP l-1 ,
frequency and other site-specific parameters
- 8. Confirm A1WS success C-2 criteria
- 9. Confirin RHR success SC-1 criteria
- 10. GE to justify CCF C-3 data -
- 11. GE to justify 0-5 train-level CCF approach is adequate
- 12. GE to justify test C 4A l' and maintenance data l analysis 13._GE to perform CDF C-4B sensitivity to outage times and surveillance l
intervals l
l l
l l
- 14. GE to justify RHR, 0-6 dPCF pump failure data
- 15. GE to correct S-Il credit taken for fire water
- 16. GE to provide write 0-22a, 0-228 up on PRA as a design tool
- 17. Staff questioned S-5 TO S-8, 1-14 seismic capacity of the following equipment:
fuel assembly, flat-bottom tank, diesel generator, electrical equipment
- 18. Staff proposed use S-10 of LLNL hazard curves
- 19. GE to address SA-1 hazard curve uncertainties
- 20. GE to confirm 1-10, 0-218 seismic capacities of equipment and incorporate into design specifications ,
- 21. GE to modify I-11 seismic PRA to account for soil structure
- failures
'22. GE to commit COL' l-12 applicant to a specific seismic walkdown technique.
i 23. GE to commit COL. 1-13 applicant to perform a site-specific seismic PRA I
24..GE to correct the .S-3 treatment of firewater L in the Seismic Class 11 I
CET
._- ._ . .___ _ _ ._.. . ~ . . _ ._. _ _ _ _ ._ .. _ -.._ _ _._. _ _ . . _ _ _ _ - - _ _ ._ _
25 GE to link PRA IN-1
'; " requirements" and .
insights to " Interface ,
write up" ,
- 26. GE to submit a fire 0-12 PRl,
- 27. Determine if CETs 0-13B need to address wetwell-drywell bypass
- 28. hodify CETs for 0-17A, -178 severe accident phenomena
- 29. Flashing during C-6 venting
- 30. Justify aspects of 0-14 rupture disc set point
- 31. Assess the impact structural calculations 0-16A, 0-18E.
of CCI on containment under review by ECGB and integrity are not a PRA issue.
- 32. Assess the impact 0-168, 0-18E.
of CCI on source terms 33.Dncertainty 0-18A, -18B, -16C
- . Analysis Identify risk '
significant issues from previous BWR studies Screen issues for applicability tc
. ABWR
- 34. Rupture disc S-9 operation before 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> -
- 35. Treatment of ATWS In the DSER, ATWS was S-12 as a late containment treated as an-early failure in CET analysis containment failure in the staff's assessment..
However.-the staff recognized in the DSEP that this should be corrected.
l' y -$ --
yT-T-Tv v ** s--+,w'---- *
. i 36, GE to provide 0-18A, 0-11 ,
1evel-1 PRA uncertainty analysis -
- 37. Drywell Sump (SCSBissue)BA-3 penetration by corium
- 38. Credit for COPS S-4 '
- 39. Drywell Head BA-1 (Bagchi)
Ultimate Strength
- 40. Service level C for BA-2 (Bagchi)
Containment
- 41. Consequence CA-3 .i Analysis '
- 42. EP7 Consequence CA-4 Analysis
- 43. Consequence CA-1 Analysis and Site '
Acceptability -
Appendix 2A I
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IS$UE DESCRIPTION STATUS ACTION OflLLUUD
- 1. GE needs to take its GE has submitted only a few GE's action to informal sebmittals and of the SSAR updates. Staff submit followed by write them up in the expects GE to provide the staff's review SSAR. majority of its SSAR of these submittals.
updates on PRA issues in December 1992 and January -;
1993.
- 2. GE is to analyze GE's previous submittals on GE submited LOCAs outside of these LOCAs were not reanalysis on ll/S.
contair' '
s (0-4) acceptable to the staff or This analysis also the ACRS. GE and the staff is to address bypass !
have discussed what needs potential for to be submitted. drywell purge and inceting lines (19E.2.3.3). Staff ;
is reviewing. 0-4B
- 3. RWCU as a high ACRS identified concerns GE to submit pressure DHR source with GE's design and requested assumptions. GE has agreed information. No to "make the PRA come date has been true." The staff is provided by GE, but '
awaiting information on it should not be isolation signals that protracted. SC-2 could isolate the entire RWCU. GE has submitted preliminary modifications to the RWCU to allow itsto remove decay heat at high pressure. GE has RWCU-related COL action items to add to its SSAR.
- 4. GE is to list Outstanding questions GE to submit. 0-21A assumptions / reliability include listing of systems values for systems that important to safety but not are not part of the modeled in PRA; Systems certified design, but modeled in PRA but not part are modeled in the PRA of Design Certification (e.g., UHS and Reactor Service Water Pump House);
Awaiting reliability assumptions for those systems modeled in'PRA.
1 9 N gy .cg ~ p e--pw r -- <- y- yq ,g.---=,-i."T T M 9- "-S.r.. . ppg * .---iwm+-w e-m. -,g m e.
- 5. GE to requantify PRA GE has submitted its GE to submit.
, based on an up-to-date updated requantification. Should not take GE a plant model There are a series of long time to questions outstanding complete. PRA-1A related to this submittal.
- 6. GE to provide GE has not provided seismic GE to submit. No seismic capacities of capacity figures for the date given, systems not in the Reactor Service Water Pump certified design House.
- 7. Uncertainty Analysis GE to provide data on GE to provide
- Treatment of wetwell- applicability of vacuum additional drywell bypass in CET breaker operating information to experience data to ABWR support vacuum (10/27/92). GE provided breaker leak test ordering of top events in data. 0-10G CET on 11/3.
- 8. Severe Accident The significance of steam Based on 10/1/92 Closure explosions in ABWR is meeting, GE to (1) reduced by having a dry reassess the cavity at the time of potential for vessel failure. Additional flooded cavity at information on the vessel failure and frequency of a flooded (2) provide cavity was requested during chronology for 10/1/92 meeting to support additional cases closure of this issue. reported in SSAR (This information was not provided in the November 3, 1992, Fax). NRC-1 e
S
e e
- 9. Accident management Staff evaluation provided GE to develop and to GE in draft Severe submit additional Accident Closure chapter. guidance for COL GE's planned response applicant on aspects discussed 10/5/92. of ABWR design which should be addressed ,
by applicant in developing their accident management plan. NRC-2
- 10. SAMDA submittal Revised SAMDA analysis GE to modify
- submitted 6/30/92 and submittal to address discussed with GE 10/8/92, concerns discussed during 10/8/92 meeting. NRC-3
- 11. Containment GE has proposed to address GE to reevaluate isolation failure this issue by extending seismic issue after during seismic event analysis of LOCAs outside completing analysis c.ontainment (19E.2.3.3) to . of issue for seismically-initiated internal events, events. The approach for Now being addressed analysis of LOCAs outside as part of revised .
containment (for internal seismic margins events) was subsequently analysis. (0-4,0-rejected by staff and is 19) now being addressed as issue 0-4.
- 12. AC Power Recovery GE submitted .
reassessment of 0.6 value assumed for probability of recovering AC power on 11/3/92.
- 13. GE to provide PRA GE still has to provide a insights discussion of balance of prevention and mitigation, improved discussion of vulnerabilities.
- 14. GE to provide decay The staff has sent GE a 0-20
. heat removal list of formal questions, reliability study y , ,m-- - e ~, - . , , - - - -,-% .- -,
. analysis the effect of high pressure pipe breaks on the walls between divisions.
Analysis expected from GE in mid-December.
- 16. Human factors in GE made related submittals GE to provide PRA (C-5, 0-7 thru 0- on sentitivity of CDF to response. C-5 to I-10, 1-2 thru l-7) human error (10/16/92 and 7 6/1/92), identification of human errors in Level 1, level 2, and seismic analyses (6/25/92), and PRA data uncertainty analysis (6/18/92). Staff requested additional information on 10/27/92.
- 17. GE to provide PRA- The staff has discussed The staff i1as based seismic margins with GE its concerns with transmitted guidance analysis the ABWR seismic margins on performing a PRA-submittal and has based margins transmitted questions to analysis for GE. GE has responded by evolutionary fax and meeting handouts to designs. SA-2 many of these questions. ,
- 18. GE to provide PRA- GE has submitted its The staff has based input to ITAAC version of PRA-based ITAAC transmitted its insights. comments to GE on
e 4
e
.19. Site specific The staff's draft SECY The staff's action design verification: paper on Design is to modify the i external floods,- Certification and Licensing siting criteria for transportation hazards Policy issues Pertaining to the ABWR since no i Passive and Evolutionary site-specific !
Advanced Light Water external flooding ;
Reactor Designs states that analysis has been 10 CFR 52.47 requires the provided. The '
analysis of both internal siting criteria will and external events. At exclude sites where the Design Certification it would be possible stage, site-specific events for external floods such as tornadoes and to exceed the height i extreme wind may be of the site grade enveloped using bounding level and where analyses to show that the other non-enveloped ,
events are insignificant. external events are i in performing the COL a threat. GE i review, the staff will. believes that it review the site-specific need not take any characteristics to ensure action at this time.
that events enveloped by I-8 the bounding analyses have been properly addressed.
- 20. Net risk impact of GE confirmed passive flooder system (11/3/92) alloy mixtures to be used in passive flooder 2
valve. 0-15
- 21. Backend Uncertainty Staff to complete Analysis - Perform review. 0-18C sensitivity analyses for issues of potential -
risk significance to
- 22. Uncertainty Staff to work with Analysis - Treatment of BNL contractors to CCI coolability in CET address risk significance of issue in FSER. (0-18E,0-16) 4
-- rrri- 7---s*1- -te-e 9 O- =m-- v' e-+--+ 7 m --r' ve- a y v ry 7 'sevMWem y
- 23. Onesrtainty GE to provide
- Ar.alysis - Treatment of justification that direct containment reactor heating in CET depressurization system is highly reliable during seismic events (CEB92-41-2). GE submittal on 11/3/92 only partly addressed this. GE still has to address reliabiltiy/
vulnerability of ADS function in seismic.
Also has to address wetwell spray availability and containment response.
Based on 10/1/92 meeting, staff to review information '
provided in 19E.2.1.2.2 re:
ability to depressurize Class-IB sequences. Staff to document evaluation in FSER.
0-18D >
- 24. Consequence related Significant differences Staff to work with issues (CA-1,2,3) observed between BNL and GE BNL contractors to consequence calculations reflect differences for apparently similar between codes.in source terms were noted FSER, during 10/1/92 meeting.
Based on follow up
- discussion on 10/28/92 differences appear to be due to use of MACCS versus CRAC2.
-y ,-- -
l: .
- 25. GE is to analyze The Reactor Systems Branch SRXB. 0-3 interfacing LOCAs is not satisfied with the resolution prcposed by GE -
for its upgrading of low pressure system piping.
This issue will remain open until GE/ staff agree on upgrade criteria and the staff PRA people can. review it to determine.if the resolution has any negative effect on its conclusions.
GE has submitted its proposed resolution to this issue.
- 26. GE to compare PRA GE's original submittal GE submitted its sequences from discussed this in write up. Under operating BWRs to the generalities. The staff staff review. 0-1B ABWR PRA sequences and wants a comparison of identify why ABWR has sequences with an lower CDF explanation of why the ABWR design results in such significant C0F reductions.
- 27. GE to use PRA GE submitted its revised Under staff review, insights to suggest RAP input on November 11, I-)5 ,
areas to be added to 1992. Rest of revision due the ABWR reliability 12/4/92.
assurance program e
. . - - - , ,sp. ,4 -. , , - . . . - - . - , y - e
The followino are SPSB issues
- 28. Fuel-Coolant Staff pursuing independent Interaction analysis of FC explosion.
- 29. Core Debris HACEIBhadheatfluxps Coolability/ Core greater than 100 kW/m for Concrete Interaction first nine hours. Staff ex1auating less than that for upper heat flux. Steff evaluating sump design.
Pedestal structural integrity under discussion.
- 30. Containment Bypass Severe accidents demonstrated .6f t',with fire water. 0.lft demonstrated w/o fire water. GE to document further information on DBA analysis.
- 31. Compliance with EPZ CA-6 Emergency Plan Criteria and Methodology O
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