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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20202H8821997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl IA-97-428, Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl1997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl ML20202H8981997-10-27027 October 1997 FOIA Request for Listed Pages from Section 19 of General Electric ABWR SSAR ML20210J3591997-08-11011 August 1997 Transmits Revised Fda for Us ABWR Std Design,Per App 0 of 10CFR52.FDA Allows ABWR Std Design to Be Ref in Application for Const Permit or Operating License,Per 10CFR50 or in Application for Combined License,Per 10CFR52 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 NUREG-1503, Forwards Suppl 1 to NUREG-1503, FSER Re Certification of ABWR, Provided for Info & Use.Suppl Documents NRC Review of ABWR Design Since Issuance of FSER in Jul 19941997-06-19019 June 1997 Forwards Suppl 1 to NUREG-1503, FSER Re Certification of ABWR, Provided for Info & Use.Suppl Documents NRC Review of ABWR Design Since Issuance of FSER in Jul 1994 ML20148A5701997-05-0202 May 1997 Forwards Affirmation Ltr Complying W/Filing Requirements of 10CFR52.45(d) & 50.30(b) Re Application for Review of ABWR Design Control Document,Rev 4 for Design Certification ML20196F8771997-03-28028 March 1997 Forwards Licensee ABWR Design Control Document,Rev 4 to Incorporate Changes Needed to Reflect Commission SRM Decisions & Subsequent Discussion W/Staff & to Support Ssar ML20137G3161997-03-28028 March 1997 Forwards Rev 4 to GEs ABWR Design Control Document to Incorporate Changes That Are Needed to Reflect Commission SRM Decisions & Subsequent Discussions W/Staff ML20147C1041997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for ABWR Before Sent to Ofc of Fr for Publication.Request Denied ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor 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 ML20117H3311996-08-30030 August 1996 Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk ML20115C0861996-07-0101 July 1996 Forwards GE Providing Background for Need for Proposed Changes to ABWR Design Control Document (Dcd), Markups Incorporating Comments Resulting from Interactions W/Nrc & DCD Markups for Addl Proposed Change ML20115G2201996-06-10010 June 1996 Provides Comments from Two NRR Organizations on Cdm & SSAR Change Pages.Markups of DCD & SSAR Encl ML20108D4481996-04-26026 April 1996 Responds to Staff Ltr Re ABWR DCD Change Package Which Recommends That GE Submit All Changes Identified by Foake Program.Ltr Contrary to Previous Understandings ML20107H3241996-04-16016 April 1996 Forwards marked-up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR Engineering Program ML20108D3111996-04-0303 April 1996 Forwards Marked Up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR First-Of-A-Kind Engineering Program ML20101G9021996-03-22022 March 1996 Forwards Amend 36 to Rev 8 to 23A6100, ABWR SSAR & Rev 7 to 25A5447, Certified Design Matl 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 ML20092G0171995-09-15015 September 1995 Forwards Missing Pp 103-117 from Attachment B of from SR Specker on Behalf of GE Nuclear Energy Re Response to Proposed RM for Std Design Certification of Us Advanced BWR Design LD-95-041, Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design1995-09-0505 September 1995 Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design ML20092B6431995-09-0101 September 1995 Forwards Analysis of Ocre 950812 Supplemental Comments on Design of Abwr,Notice of Final Rule & Statement of Considerations,In Order to Ensure That NRC Has Complete Technical Info on Subj ML20086G7981995-07-12012 July 1995 Informs of Changes to Svc List,Per Request of Jn Fox ML20084Q0621995-05-31031 May 1995 Forwards Revised Effective Page Listing for ABWR Design Control Document ML20078F4271995-01-26026 January 1995 Provides Info for Closure of ABWR FSER Confirmatory Item F1.2.2-2 Previously Addressed in 941222 Closure Ltr ML20077R9141995-01-17017 January 1995 Forwards Rev 2 to ABWR Design Control Document. Rev of Design Control Document Accompanied by List of Currently Effective Pages.List Provided as Attachment 2 ML20081K9361994-12-22022 December 1994 Documents Closure of ABWR FSER Confirmatory Items ML20080D3341994-12-22022 December 1994 Forwards Rev 1 to Advanced BWR Design Control Document ML20077A7471994-11-23023 November 1994 Forwards Revised Fda for Us ABWR Std Design,Per App O of 10CFR52 & Notice of Issuance of Fda ML20081K9031994-11-18018 November 1994 Forwards Rev 0 to Technical Support Document (Tsd) for ABWR & Updated ABWR SSAR App 19P Markup.Updated Version of App 19P Incorporated as Attachment a to Tsd,As Agreed During 941006 Meeting W/Nrc ML20073M7221994-11-0404 November 1994 Forwards Proposed Rev to Section 3.8 of DCD Introduction for ABWR Re GE Meeting on 941102 ML20078E6391994-11-0101 November 1994 Forwards Description of Proposed Process for Controlling Changes to Severe Accident Evaluations & Explains Bases for Proposed Process ML20149G9751994-10-31031 October 1994 Requests That Encl Ltrs Be Distributed to Controlled Copy of Licensee QA Program ML20149G7081994-10-28028 October 1994 Forwards Rev 0 to ABWR Design Control Document (Dcd). DCD Comprised of Introduction,Certified Design Matl & Approved Safety Analysis Matl.Responses to NRC Comments Requested by Also Encl ML20081K8881994-10-13013 October 1994 Maintains That Proposition That GE Be Designated in Notice of Proposed Rulemaking as Source from Which Public Could Request Copies of Design Control Document (DCD) Inappropriate.Public Should Obtain Access to DCD from NRC ML20076F8451994-10-0505 October 1994 Responds to Re Root Cause & Corrective Measures on Unidentified Changes That Occurred in Design Control Document ML20081K8721994-09-20020 September 1994 Requests That ABWR Final Design Approval (Fda) Be Amended to Provide for Term of 15 Years from Date of Issuance & That,As Provided in SRM on COM-SECY-95-025,FDA Be Updated as Needed to Conform to Any Changes Resulting from Certification RM ML20149F7681994-09-0707 September 1994 Forwards Rev 0 to Advanced BWR Design Control Document 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+ ML20072Q2811994-08-30030 August 1994 Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev ML20072C9821994-08-12012 August 1994 Responds to Re NRC Fee Regulations for Design Certification & Request Confirmation of Understanding of 10CFR170 ML20072E3381994-08-0909 August 1994 Requests Addition of Author Name to Svc List for Advanced BWR ML20072A8451994-08-0303 August 1994 Forwards Chapter 21 17x22 Inch Drawings to Replace Temporary 11x17 Drawings Provided in ML20071Q9091994-08-0202 August 1994 Forwards Ten Copies of Draft ABWR Design Control Document 1997-08-11
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARIA-97-428, Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl1997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl ML20202H8821997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl ML20210J3591997-08-11011 August 1997 Transmits Revised Fda for Us ABWR Std Design,Per App 0 of 10CFR52.FDA Allows ABWR Std Design to Be Ref in Application for Const Permit or Operating License,Per 10CFR50 or in Application for Combined License,Per 10CFR52 NUREG-1503, Forwards Suppl 1 to NUREG-1503, FSER Re Certification of ABWR, Provided for Info & Use.Suppl Documents NRC Review of ABWR Design Since Issuance of FSER in Jul 19941997-06-19019 June 1997 Forwards Suppl 1 to NUREG-1503, FSER Re Certification of ABWR, Provided for Info & Use.Suppl Documents NRC Review of ABWR Design Since Issuance of FSER in Jul 1994 ML20147C1041997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for ABWR Before Sent to Ofc of Fr for Publication.Request Denied ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor ML20077A7471994-11-23023 November 1994 Forwards Revised Fda for Us ABWR Std Design,Per App O of 10CFR52 & Notice of Issuance of Fda ML20059C2961993-12-29029 December 1993 Forwards Detailed Discussion of Remaining Issues & Final Position for Resolution Re ABWR Containment Sys & Severe Accident Review Issues ML20058L2041993-12-14014 December 1993 Forwards Documents Including Info on Vessel Level Instrumentation Experience at European Reactors ML20058G6591993-11-30030 November 1993 Corrects Transmitting Draft Commission Paper,By Changing Date of ACRS Meeting & Due Date for GE Comments from 931215 to 1209.Forwards Commission Paper for Distribution to GE Staff ML20058D7091993-11-22022 November 1993 Forwards Advance Copy of Draft Commission Paper, Diversity in Method of Measuring Reactor Pressure Vessel Level in ABWR & Simplified BWR, for Distribution to Appropriate GE Staff ML20058B0911993-11-15015 November 1993 Forwards Replacement Copy of Independent Quality Review Group Initial Comments on GE ABWR Certified Design Matl & Ssar,Provided During 931110 & 11 Meetings in San Jose, Including Missing Pages Due to Xerographic Error ML20059K3151993-11-0909 November 1993 Discusses GE Relief from NRC Metrication Policy for Both ABWR & Sbwr Designs ML20059L9681993-11-0909 November 1993 Forwards Comments on GE ABWR Tier 1 Certified Design Matl ML20059J1001993-11-0101 November 1993 Forwards Independent Quality Review Group Initial Comments on GE Nuclear Energy ABWR Certified Design Matl & Ssar ML20057D8431993-09-27027 September 1993 Submits Initial Staff Comments on GE ABWR Tier 1 930831 Submittal Re ABWR Certified Design Material.Submittal Adequately Reflects Agreements Reached for Tier 1 Material ML20057A4151993-08-31031 August 1993 Forwards Proof & Review ABWR TSs & Bases for Sections 3.3, Instrumentations & 3.8, Electric Power (Includes Low Power & Shutdown) ML20056H6521993-08-30030 August 1993 Requests Staff Support to Complete Scope of Insp to Be Conducted at Facility in San Jose,Ca on 930907-10.Insp to Review QA Programs ML20056H6341993-08-26026 August 1993 Responds to Several Informal Inquiries from Design Certification Applicants Re Form & Content of Design Control Document.Forwards Current Staff Views Re Document ML20056G0531993-08-18018 August 1993 Requests That Corrected Pages Encl Be Used to Replace Pages Inadvertently Included in Staff Review Comments on Generic Issues Re ABWR ML20056F2961993-08-17017 August 1993 Forwards Comparative Mark Up of Insights List Showing Differences Between 930723 Version & 930810 Version ML20056G1671993-08-17017 August 1993 Forwards Proof & Review Advanced BWR TSs for Low Power & Shutdown.Anticipates That Formal Comments to Proof & Review Advanced BWR TS Will Be Made by 930920 ML20056F4191993-08-12012 August 1993 Provides Staff Review Comments on GIs Re ABWR Design.Advises That GE Has Not Sufficiently Addressed,In Revised SSAR mark-ups,all Comments & Concerns Previously Provided by Staff ML20056H5161993-08-10010 August 1993 Forwards Proof & Review ABWR TS & Bases for Sections 3.6, Containment Sys & 3.7, Plant Sys. Informs That Sections as Provided Acceptable ML20056F4901993-08-10010 August 1993 Forwards Proof & Review of ABWR TSs & Bases for Sections 3.6, Containment Sys, & 3.7, Plant Sys ML20056G0331993-07-30030 July 1993 Forwards Proof & Review ABWR TS for Listed Sections.Info in Preparation for 930819 & 20 Meeting Also Encl ML20056D4791993-07-23023 July 1993 Forwards Proof & Review ABWR TS & Bases for Sections 3.4 RCS,3.5 ECCS & 5.0 Administrative Controls (No Bases) ML20046C7301993-07-21021 July 1993 Forwards Draft Safety Issues Index,Generic Issue Review Assignments,Status of ABWR USI-GSI Review & Staff Comments Provided During Conference Calls ML20046C3781993-07-15015 July 1993 Forwards Proof & Review ABWR TSs & Bases for Listed Sections ML20045H0441993-07-0909 July 1993 Forwards Staff Comments on GE ABWR Tier 1 Submittals Dtd 930426,0521,0604,18,21 & 29.Advises That GE Should Revise Tier 1 Design Certification Matl to Resolve Comments & Provide mark-up Immediately ML20045F9641993-07-0707 July 1993 Informs That NRC Voted to Exempt ABB-CE Sys 80+ Design Certification from NRC Policy on Metrication & Requests That Licensee State Whether or Not to Be Relieved of Responsibility for Performing Conversions ML20045G6921993-07-0202 July 1993 Forwards Proof & Review ABWR TS & Their Bases for Sections, 3.1,reactivity Control & 3.2,power Distribution ML20045G6021993-07-0202 July 1993 Forwards Proof & Review ABWR TSs & Bases for Listed Sections ML20045E6631993-06-29029 June 1993 Forwards Proof & Review ABWR TS & Bases for Sections Listed ML20045D9281993-06-25025 June 1993 Forwards Chart of Milestones to Develop ABWR TSs as Discussed During Mgt Meeting on 930610 ML20046C5791993-06-16016 June 1993 Forwards Preliminary Drafts of Low Power & Shutdown TS Proposed for BWR Current Designs ML20036B9691993-05-28028 May 1993 Forwards Staff Comments & Questions Re ABWR TS Issues ML20044G9851993-05-26026 May 1993 Discusses GE 930305 Request for Deviation Re ABWR Design Basis Loading Combinations.Nrc Has Not Endorsed Use of Probabilistic Approach as Basis for Decoupling SSE & LOCA Loading Combination.Response Requested ML20036A4701993-05-0505 May 1993 Discusses Review of Providing Response to Preliminary Evaluation of Info in Advanced BWR SSAR Classified as Proprietary Info by GE Nuclear Energy ML20035H7291993-04-29029 April 1993 Responds to Licensee Commenting on Importance of Completing Reviews of Both ABWR & Sys 80+ Designs as Quickly as Possible ML20035G0131993-04-21021 April 1993 Forwards Info Gathered from Comments Received from NRC Contractor on ABWR Internal Flooding Analysis ML20035F7121993-04-19019 April 1993 Forwards Thoughts Put Together from Comments Received from Contractor on Advanced BWR Shutdown Analysis ML20035A6901993-03-12012 March 1993 Documents Conference Call on 930311 W/Licensees Re ECCS Pump Qualifications & Class II Sequences ML20034H7661993-03-0909 March 1993 Retransmits Addl ABWR PRA Questions,Previously Sent on 930123 ML20034G4991993-03-0404 March 1993 Forwards Summary of Chapter 3 Issues, Design of Ssc ML20034G1361993-03-0404 March 1993 Forwards Markups from Human Factors Branch on Advanced BWR ITAAC & Chapter 18,App E of Ssar.Vendor Should Be Prepared to Discuss Items During 930305 Telcon 1997-08-11
[Table view] |
Text
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March 4, 1993 Docket 52-001 NOTE TO:
JACK FOX, GE FROM:
MIKE JANUS, NRR/ADAR/PDST
SUBJECT:
SUMMARY
OF CHAPTER 3 DISCUSSIONS WITH B. BURTON Enclosed is a summary of Chapter 3 issues, their status and important dates, prepared by B. Burton in response to the recently held teleconference calls involving these issues.
Please call me at 301-504-3139 if you have any questions.
Document Control Room ((
cc:
Chet Poslusny 050002 9303090606 930304 PDR ADOCK 05200001 A
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3/4/93 ABWR DFSER OPEN. CONFIRMATORY. COL ACTION. AND INTERFACE ITEMS
_QJiAPTER 3 - DESIGN OF SSCs SSAR SECTION 3.4.1 - FLOOD PROTECTION OPEN ITEMS
- 3. 4.1-1 Provide flood analysis for turbine building.
RESOLVED (Confirmatory): 3/2/93 Phone call with GE. 10.4.5.5 is wrong reference.
It should be 10.4.5.6.
This reference will be changed to include the response from 430.73(b) regarding flooding in tqe Turbine Bldg from a break in CW piping.
The 2.15 meters will be changed to 5 meters. Table 3.4-1 will be changed as follows:
1.
Bldg heights for S/B, CB, Rw/B,-
and TB are changing.
2.
Tunnel between RB and SB is at 4800mm.
3.
Tunnel between CB and SB is Access at -2150mm.
4.
Tunnel between RB,
- RwB, and TB slopes from S800mm at RB (1.2-24) to 1500mm at RwB (1.7-23a).
3.4.1.1.2.5 uill state that all ends of tunnel are sealed.
5.
Tunnel between TB and SB is Access at 7900mm (1.2-24.
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CONFIRMATORY ITEMS 3.4.1-3 Provide information regarding provisions to protect the control room from the effects of a pipe failure in the i
RSW piping in the control building.
RESOLVED (CONFIRMATORY): 3/2/93 phone call. GE will change SSAR from 2.15 meters to 5 meters.
SSAR SECTION 3.5.1.2 - INTERNALLY-GENERATED MISSILES (INSIDE CONTAINMENT)
QEEN ITEMS 3.5.1.2-1 Provide information showing that housing for rotating equipment can contain missiles or make this a COL Action Item.
RESOLVED (Confirmatory): 3/2/93 GE phone call.
No Non-Proprietary document will be provided.
SER must state that Proprietary document was used. SSAR Section 3.5.5, Reference 1 will be changed back to what it was before.
COL ACTION ITEMS l
3.5.1.2-1 Provide procedures to ensure that equipment undergoing maintenanca will be removed from containment during operation or will be seismically restrained.
RESOLVED (CONFIRMATORY): 2/26/93 fax changed 3.5.1.2.4 and added 3.5.4.7. This is acceptable, i
t NOTE:
Change DFSER p.
3-15 (top of page) to refer to only motor-driven rotating machinery, not all rotating j
machinery.
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SSAR SECTION 3.5.1.4 - MISSILES GENERATED BY NATURAL PHENOMENA i
COL ACTION ITEMS i
1 3.5.1.4-2 Provide information on protective features against I
missiles identified in 3.5.1.4-1 above.
i OPEN:
3/2/93 GE phone call. GE says letter to PM (2/3/93) states that this is discussed in Chapter 2.
If so, This section needs to refer to Ch.
2.
I need to check this (3/10/93).
SSAR SECTION 3.5.2 - SSCs PROTECTED FROM EXTERNAL MISSILES t
COL ACTION ITEMS 3.5.2-1 Provide information concerning protection of safety-l related equipment from missiles generated by SSCs outside the ABWR design scope.
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RESOLVED (CONFIRMATORY): 2/26/93 fax from GE added 3.5.4.8.
l This is acceptable.
NOTE:
Section 3.5.4.5 still not correct. GE will change it (3/2/93 phone call) l I
SSAR SECTION 3.6.1 - PIPE FAILURES CONFIRMATORY ITEMS 3.6.1-1 Remove references to LBB l
CLOSED:
3/2/93 phone call. GE will keep the LBB references in the SSAR but make clear that no credit is taken for LBB and the LBB is an option that the referencing applicant MAY use if he chooses.
3.6.1-2 Modify Table 3I.3-15 to reflect worst case pressures (assuming failure of blowout panels to function properly).
3
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3/2/93 phone call. GE is redoing the subcompartment pressurization analysis. When that's done, Ch. 6 and Ch. 3 will be modified and the chapters will agree.
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COL ACTION ITEMS 3.6.1-4 Provide details on protection provided against the effects of piping failures to ensure main steam line isolation valve functional capability.
t CLOSED:
3/2/93 phone call. GE clarified that this is a COL Action Item.
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i SSAR SECTION 3.11 - ENVIRONMENTAL OUALIFICATION OPEN ITEMS 3.11.3-2 Show that GEs position regarding radiation protection for electronic components agrees with that of the staff.
RESOLVED (Confirmatory): 3/4/93 phone call. GE will clarify that electronic equipment exposed to
>= 1000 R is considered to be in a harsh environment and will be qualified in accordance with 10 CFR 50.49.
Other electrical equipment exposed to >= 10,000 R is considered to be in a harsh environment and will be qualified ina ccordance with 10 CFR 50.49.
Harold will provide guidance on qualification of mechanical equipment.
3.11.3-3 Explain why ABWRintegrated gamma accident dose is lower than doses for operating reactors.
1 RESOLVED (Confirmatory): 2/25/93 submittal regarding this is being reviewed by Harold Walker and Jay Lee. Response by 3/10/93.
CONFIRMATORY ITEMS 3.11.2.1-1 Confirm that SSAR Section 3.11.1 will be updated to
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reflect compliance with NUREG-0588 and RG 1.89.
OPEN:
3/4/93 phone call. GE will change to specify RG 1.89.
3.11.3-3 Update. figures 3I.3-1 through 31.3-22 to include references to P&ID and IED drawings that will identify typical equipment for each zone.
RESOLVED (CONFIRMATORY): 3/4/93 phone call.
Harold is reviewing. Response 3/10/93.
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3.11.3-4 Update SSAR to include Table 3I.3-A and amended Appendix 31 tables to contain thermodynamic environmental conditions for both normal operating conditions and design basis accidents in order to develop time-based profiles for various identified Zones.
OPEN:
3/4/93 phone call. GE will clarify installed life for equipment, total integrated dose, and remove references to SSAR section 12.2.3.1 and substitute a reference to the shielding DAC (3.7a) or, if references can't be made to the ITAAC in the SSAR, the words from the DAC will be used in the SSAR. GE will review the pressure and temperature values in the 3I tables after the new subcompartment pressurization analysis is done.
COL ACTION ITEMS l
1 3.11.3-1 Address issues identified in IN 89-63 related to flooding above the flood level and equipment wetting.
CLOSED:
3/4/93 phone call. GE will ensure that terminology used in IN 89-63 is used in the SSAR. " Wetting" may_
not be appropriate.
3.11.3-2 Evaluate radiation effects on equipment.in harsh zones for both normal operations and accident
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conditions.
t OPEN:
3/4/93 phone call. GE will clarify installed life l
for equipment, total integrated dose, and remove Leferences to SSAR section 12.2.3.1 and substitute a reference to the shielding DAC (3.7a) or, if references can't be made to the ITAAC in the SSAR, the words from the DAC will be used in the SSAR. GE
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will review the pressure and temperature values in the 3I tables after the new subcompartment pressurization analysis is done.
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i NOTES:
1.
3.11.2 should reference IEEE 323-1974 L
2.
- p. 3.11-11.1 is incorrect. It should be 3.11-1.1.
t 3.
Change Section 3.11.6.2 to read "....in accordance f
with Reference 1."
4.
- p. 3.11-1.1 should read ".... safety function within minutes.
5.
SSAR should be changed to reference new App. 3K instead of topical report.
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- j Safety-Related Mechanical Equipment in a Harsh Environment Although there are no detailed requirements for mechanical equipment, G
" Quality Standards and Records," and 4, " Environmental and Missile D and Appendix B to 10 CFR S0, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" (Section III, " Design Control," and XV
" Quality Assurance Records"), contain the following requirements related to equipment qualification:
Components shall be designed to be compatible with the postulated environ-mental conditions, including those associated with LOCAs.
Measures shall be established for the selection and review for suitabilit of application of materials, parts, and equipment that are essential to safety related functions.
Design control measures shall be established for verifying the adequacy design.
Equipment qualification records shall be maintained and shall include the r
results of tests and materials analyses.
For mechanical eouipment, the staff review will concentrate on materials which are sensitive to environmental effects, for example, seals, gaskets, lubricants, fluids for hydraulic systens, diaphragms, etc. A review and evaluation should be performed by the applicant that includes I
the followino :
(1) Idedtification of safety-related mechanical equipment located in harsh environment areas, including required operating time.
i (2) Identification of non-metallic subcomponents of this equipment.
(3) Identification of the environmental conditions this ecuipment
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must be cualified for.
The environments defined in the electrical equipment program are also applicable to mechanical equipment.
(41 Identification of non-metallic material capabilities.
(5) Evaluation of environmental effects.
The list of equipment identified should be submitted.
From this list the staff will select approximately three items of mechanical equipment for which documentation of their environmental qualification should be provided for review.
Also, the results of the review should be provided f
for all mechanical eouipment in harsh environment areas and corrective actions identified.
' ' * * ~ ~ ~