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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 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 Ge'S 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 ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor 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 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 ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs 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 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 ML20070H9651994-07-20020 July 1994 Forwards Rev 7 to 23A6100, ABWR Ssar, Amend 35 & Rev 6 to 25A5447, ABWR Certified Design Matl 1997-08-11
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor 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 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 ML20059L9681993-11-0909 November 1993 Forwards Comments on GE ABWR Tier 1 Certified Design Matl ML20059K3151993-11-0909 November 1993 Discusses GE Relief from NRC Metrication Policy for Both ABWR & Sbwr Designs 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 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 ML20056F2961993-08-17017 August 1993 Forwards Comparative Mark Up of Insights List Showing Differences Between 930723 Version & 930810 Version 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) ML20128L7201993-02-18018 February 1993 Forwards Changes to Dfser Chapter 9 Section 9.3.5 Re Reliability of Suction Valves for Slcs,Per 930217 Discussion ML20128L7131993-02-16016 February 1993 Forwards Proposed Agenda for 93022-26 Audit.Suggests That Licensee Provide Copy of Encl to NRC & Bechtel to Facilitate Understanding of Scope of Audit ML20128G8721993-02-12012 February 1993 Forwards Guidance Documents Re Teir 2 Info Considered in Preparation of Ssar Revs to Complement ITAAC Items Discussed in Recent Meetings W/Mem Staff ML20128N5111993-02-11011 February 1993 Forwards Summary of 930111-27 Meeting W/Licensee Re ITAAC ML20127P4671993-01-26026 January 1993 Discusses Audit of ABWR Structural Design to Be Held 930222-25 Re Review of Design Calculations to Close Out Open Items Identified in Draft Final Safety Evaluation Rept ML20127M6941993-01-25025 January 1993 Discusses Preliminary Staff Evaluation of ABWR Severe Accident Performance ML20127D0761992-12-28028 December 1992 Forwards Requested Clarification That Deals W/Areas of GE Chapter 19,App K Submittal (PRA Input to Reliability Assurance Program) ML20126F7601992-12-23023 December 1992 Discusses Status of GE Nuclear Energy Advanced BWR Shutdown Risk Draft FSER ML20127D6591992-12-22022 December 1992 Forwards List of Clarifications Needed to Complete NRC Review of LOCA Outside Containment for Advanced BWR PRA ML20126G0771992-12-21021 December 1992 Forwards Preliminary Safety Evaluation for Info Provided by GE Re Capacity of Reinforced Concrete Containment Vessel in App 19F of Ssar.Advises That Addl Info Necessary ML20127D6351992-12-21021 December 1992 Forwards Proposed Scope of Operating Experience Review Re Resolution of Open Item in Draft,Final SER for Human Factors Engineering Design for Advanced BWRs ML20126A2901992-12-15015 December 1992 Forwards Preliminary Evaluation of ABWR Design for Instrumentation & Control Diversity,Per Open Item Noted in NRC Draft Final Ser.Most of Item Satisfactorily Resolved. Expects Discussion of Diversity Issue at 930121 Mgt Meeting ML20128D1211992-12-0202 December 1992 Forwards SE Accepting GE Proposal for Implementing ISLOCA Issue Resolution for Advanced BWR ML20127D1141992-12-0101 December 1992 Forwards Items Identified as Result of Staff Review of GE Advanced BWR Shutdown Panel Instrumentation Inventory.W/O Encl ML20127D3261992-09-0202 September 1992 Requests That Schedule Be Provided Consistent W/Resolving Identified Concerns Re Ssar App 19P, Evaluation of Potential Design Mods to ABWR, by Middle of Oct 1992 1997-08-11
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P UNITED STATES f" \ NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
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- e k.....8 ,o January 23, 1997 OFFICE OF THE SECRETARY Mr. Steven A. Hucik General Manager Nuclear Plant Projects l GE Nuclear Energy ,
l 175 Curtner Avenue, M/C 780 !
San Jose, California 95125-1088
Dear Mr. Hucik:
I am responding to your December 16, 1996 letter requesting an opportunity to review the design certificstion rule for the Advanced Boiling Water Reactor t (ABWR) before it is sent to the Office of the Federal Register (0FR) for l publication. Your letter indicates that the purpose of this review would be narrowly limited to focus solely on ensuring that the language of the rule accurately and clearly conforms with the Commission's policy determinations as set forth in the Commission's Staff Requirements Memorandum (SRM) of December 4,1996, and would not be for the purpose of commenting on the policy l determinations that have been made by the Commission. You also state that GE I Nuclear does not intend to raise new issues, and that any meeting between GE Nuclear and the Staff would be publicly noticed.
The Commission has decided that a limited opportunity for GE Nuclear to review the final ABWR design certification rule solely for the purpose of ensuring I l that the rule conforms with the Commission's SRM is not necessary. In light i of the extensive public process leading to the specification of the issues decided by the Commission's SRM, the specificity of the Senior Review Group's August 13, 1996 Memo to the Commission which addressed these issues, and the detailed direction provided in the Commission's SRM, a further limited review l opportunity by GE Nuclear would not provide any substantial enhancemer$^ to the
! quality of the final design certification rule. 'r l Sincerely, i
IA _
hn C. oyle Secretary of the Commission l
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.lun.kse, c4 9S1261068 408 92S 6951 h:4069254267 December 16,1996 I Mr. John C. Hoyle, Secretary i OfEce of the Secretary Nuclear Regulatory Commission
, Washington, D.C. 20555
Dear Mr. Hoyle:
1 l Sub)ect: Design Corts)ication Rulefor the Advanced Bel ling WaterReactor i (ABWR); Docket No.32-001.
! On December 4,1996, the Commission issued a Staff Requirements Memorandum j (SRM) approving certification rules for the ABWR and System 80+. In so doing, the
- Commission resolved the remaining policy issues and directed the staff"as a matter of
! priority to couform the final certificadon rules to the changes noted in the SRM and l forward the rules to the Secretary for signature and publicadon in the Federal Register.
- General Electric (GE) is deeply appreciative of the Commission's constructive resolution j of the policy issues and the emphasis it placed on priority compledon of the rulemaking process.
GE is the apphcant for design certification of the ABWR. Based upon discussions with 4
Mr. Jerry N. Wilson of the NRC staff, we were informed that the staff will complete work on the design certification rule for the ABWR in approximately three or four months, that the rule will be provided to the Secretary for transmission to the Office of Federal j Register (OFR), and that we will not be given an opportunity to see the rule before it is
- sent to the OFR unless the Secretary's Office so authorizes. The purpose of this letter is
- to request your authorizadon for GE to conduct a narrowly focused review of the design certification' rule for the ABWR before it is sent to the OFR and to urge that staff rule issuance activities be expedited to the maximum extent feasible. We believe that both requested actions can be mutually supportive in carrying out remaining NTC pre-issuance steps.
- As you are aware, a supplemental proposed rule for design certification of the ABWR was issued for public comment in SECY-96077. OnJuly 23,1996, GE submitted extensive comments on the design certification rule for the ABWR, and incorporated by reference the lengthy comments submitted by the Nuclear Energy Institute (NEI) on the same date.
Based upon requests by NEI, the Commission established a Senior Review Group (SRG) to review these comments, and the SRG issued an extensive analysis of these comments on August 13,1996 recommending a number of changes to the supplemental proposed rule contained in SECY-96-077. SRG recommendations on other issues raised in industry comments were contained in the memorandum to the Commission from the Executive Director for Operations dated October 21,1996., in a SRM dated December 6,1996, the A./
12/19?..To OGC to: Prepare Response for Signature...Date due: Jan 6 Cpy to: Chairman, DSB.. 96-1256
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f ., P. 24 DEC 19 '% 11:22At1 2
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4 Mr. John C. Hoyle, Secretary
- December 16,1996 j Page 2 i
i
- Commission accepted most of the SRG's recommendations and identified other areas in I which the supplemental proposed rule should be modified.
i j As a result of the Commission's SRM, all policy issues regarding the design certification j mie for the ABWR have been resolved. However, in most cases, neither the SRG's August ,
i IS and October 21,1996 analyses nor the Commission's SRM identi6ed specific language -!
j to implement these resolutions for the issues raised by NEI and GE. Because the implementing language is cdtical to the resolution of these issues, we request an ;
- opportunity to mview the design certification mie for the ABWR before it is sent to the ,
j OFR. Our review would be narrowly limited -it would focus solely on ensuring that the l j language of the rule accurately and clearly conforms with the resolutions specified by the !
! Commission; we are not requesting an opportunity to comment on the policy l determinations that have been made by the Commission and we do not propose to raise new issues. Any such meeting for this purpose would, of course, be publicly noticed. j For the following reasons, we believe that it would be appropriate to allow GE to conduct -
such a narrowly-focused revicw:
- GE is the applicant for design certification of the ABWR. As the applicant, we have a unique interest in ensuring the accuracy and clarity of the design certification rule.
In this regard, we note that the NRC in the past has given applicants for operating l licenses for nuclear power plants an opportunity to review the licenses before they are {
issued in final form, and we believe that it is appropriate to afford GE an analogous ;
opportunity to review the design certification for the ABWR before it is 6nallacd. ;
(
- The SRG and Commission accepted many of the comments submitted by GE !
(including NEI's comments that GE incorporated by reference). Therefore, we i believe that GE can provide an especially valuable function in ensuring that the l language in the design certification rule accurately and clearly reflects the Com- l mission's intent. Review by GE of the implementing language will help ensure a ;
r quality product. In this regard, we note that we have previously identified clarifiations and corrections in the language of the proposed rule and supplemental proposed ;
rule, and both the staff and the Commission have found these clarifications and j corrections to be useful and appropriate in implementing the content of the i Commission (see, e.g., the Commission's SRM dated March 17,1995 on SECY 95-023; SRG's August 13,1996 Analysis, @g I.E., I G., and X.A.). ;
l
- A review by GE would not delay issuance of the design certiScation mic. Indeed, we desire that the mie be issued as expeditiously as possible and that, consistent with the Commission's SRM directive for " priority" staff action, the aforementioned three to four months of pre-issuance staff activities be significantly reduced. Based i
upon our discussion with the staff, we undcrstand that the critical path to submission of the rule to the OFRis not revision of the supplemental proposed rule but instead ;
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Mr. John C. Hoyle December 16,1996 l Page 3 performance of ancillary activities, such as revising the final safety evaluation report (FSER) for the ABWR, and a lengthy period for the staff concurrence process. We estimate that GE could perform its review in one or two days, and we expect that any l clarifications or corrections could easily and quickly be incorporated into the rule.
In this regard, we understand that the Office of General Counsel (OGC) will be completing its review of the design certification rule in the next several weeks, and we -
l would propose that our review be conducted contemporaneously with or shortly after OGC's reyew.
. We have discussed the possibility of a review by GE with the NRC's Deputy General Counsel, and he has informed us that OGC has no legal objection to such a resiew.
Similarly, we are not aware of any legalimpediment to such a review.
Based upon the above, we request thatyou direct the staff to permit GE to resiew the design certification rule for the ABWR prior to its submission to the OFR for the limited l
purpose of ensuring that the language in the rule accurately and clearly impicments the Commission's resolutions of the policy issues raised by GE.
1 Sincerely, j
/-
l A g' Steven A.Hucik j
l cc: ChairmanJack. son
! Commissioner Rogers Commissioner Dicus 1
l Commissioner Diaz Commissioner McGafligan M. Malsch J. Wilson ;
l j
I