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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:INCOMING CORRESPONDENCE
MONTHYEARML20202H8981997-10-27027 October 1997
FOIA Request for Listed Pages from Section 19 of General Electric ABWR Ssar
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
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
ML20080D3341994-12-22022 December 1994
Forwards Rev 1 to Advanced BWR Design Control Document
ML20081K9361994-12-22022 December 1994
Documents Closure of ABWR FSER Confirmatory Items
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
ML20072Q2811994-08-30030 August 1994
Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev
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+
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
ML20070D9381994-07-12012 July 1994
Forwards D-RAP Design Description & ITAAC for Inclusion in Section 3.6 of Cdm & Cdm & Ssar Markups Addressing Minor Corrections
ML20069Q3001994-06-23023 June 1994
Forwards Rev 6 for Ssar Amend 35 & Rev 5 for Certified Design Matl
ML20070E1981994-06-0808 June 1994
Forwards Ssar Markup Indicating Applicable Edtion to UBC, AISI SG-673 & NEMA FB1 to ABWR Ssar.Changes Will Be Included in Amend 35 Mod Package.Notifies That Applicable Edition of Bechtel Rept BC-TOP-3-A Is Rev 3
ML20070E1891994-06-0808 June 1994
Forwards Ssar Markup of Section 1A.2.34 Which Responds to TMI Item III.D.1(1).Mod Makes Section Consistent W/Ts 5.5.2.2.Change Will Be Included in Amend 35 Mod Package Scheduled for Distribution Later This Month
ML20070D9331994-05-26026 May 1994
Forwards Results of Analyses to Assess Impact of Drywell Spray Actuation Following LOCA to Ensure Bounding Scenario
ML20069H2101994-05-25025 May 1994
Forwards 25A5447,Rev 4, ABWR Certified Design Matl & Nonproprietary & Proprietary Version of 23A6100,Rev 5, ABWR Ssar. Proprietary Version of Ssar Withheld
ML20069G9301994-05-25025 May 1994
Submits non-proprietary Ssar Amend 35 & Certified Design Material Rev 4 to Listed NRR Recipients
ML20069B1831994-05-25025 May 1994
Resubmits Affidavit for GE Abwr,Proprietary Info Section 18H, Supporting Analysis for Emergency Control Operation Info
ML20069A7371994-05-20020 May 1994
Forwards Proprietary Ssar Sections 11A.2 & 11A.4 to Specified NRR Recipients Listed on Attachment 1.Encl Withheld
ML20029D4211994-04-29029 April 1994
Forwards Revised Ssar Markups Responding to Commitments Made at 940415 Meeting in Rockville,Md,Including Addl Info Reflecting Locking Mechanisms of Subassemblies & European Experience & Finalized TS for CRD Removal - Refueling
1997-07-23
[Table view] |
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u - GENucicar Energy General!!ectac Company 175 Curtner Annae. Son Jose. CA 951?S June 18,1993 Docket No. STN 52-001 l
Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Schedule - Startup and Pre-operational Test Material
Dear Chet:
Enclosed are respon ;es to NRC comments on startup test material dated June 7,1993 and on pre-operationn' test material dated June 14,1993.
Please provi.J - " of this transmittal to Frank Talbot.
Sincerely,
- l ack1-3 Advanced Reactor Programs cc: Norman Fletcher (DOE)
IL J. Yang (GE) p
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9306240456' 930618 W
PDR. ADOCK 05200001 fi A PDR h -
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~1 Response to NRC's Comments dated 6/14/93 Preoperational Test Material open Item 14.2.12.3-2 Cross reference information within SSAR has been added to 14.2.12.1.46 and 14.2.12.1.68. There is no SSAR subsection for the hot water heating system.
However, the acceptance criteria currently existing in 14.2.12.1.31.(3) are based upon the available design document and test requirement specs. Thus, I believe that the test abstract section is adequate without the SSAR cross ref erence information.
TSI 14.2.10.1-1 and 14.2.12.4-1 J. revision to our April 16 response to DFSER TSI 14.2.10.1-1 and 14.2.12.4-1 is being prepared by Cal Tang. I have recommended to Cal on using applicable preop. tests (i.e., 14.2.12.1.6 for scram valve operability and 14.2.12.1.15 for SRNM) rather than referencing to LCOs for resolving this lasua.
Preoperational Test Program Issues ,
Section 14.2.1 The quoted paragraph from May 7, 1993 submittal was incorporated into the second paragraph of 14.2.1. I believe it would be more appropriate to add this paragraph to this location than that origir. ally specified in 5/7/1993 submittal.
Section 14.2.12.1.11 ,
The SSLC verification and validation test is a part of the preoperational phase test and covered by 14.2.12.1.11.(3). Therefore, the quoted sentence
' in Feb.12, 1993 submittal was removed from the prerequisite section. The last two sentences of Feb. 12, 1993 markup were inadvertently combined into one sentence during typing. The removed specific information will be added to the prerequisite section in Amendment 30 to be consistent with 2/12/ 1993 markup submittal.
Section 14.2.12.1.14 The quoted timing criteria is for the seal-in and reset function of the RPS trip logic circuitry. Based on the RPS design, all manual resets shall be automatically inhibited for ten seconds following a full reactor scram. This ;
verification shall be a part of the RPS preoperational testing and won't bs done in conjunction with the CRD preop, test.
Section 14.2.12.1.21 The quoted missing text per February 12, 1993 markup was removed based on a verifier's comments. The end sentence as statad needs not be repeated since ;
the flow path for FPCCU system normal mode of operation is readily specified j in the PFD.
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l section 14.2.12.1.30 l The quoted electrical instrument equipment was removed from the prerequisite i section based on a verifier's comments. It is hard to define the content of ]
electrical instrument equipment. Additionally, METES need not be specified in detail as a part of the prerequisite.
Section 14.2.12.1.43 The quoted test for verifying proper functioning of valve positive closure '
devices including valve leak tightness test was . inadvertently omitted during typing. This test item will be added to 14.2.12.1.43.(3) in Amendment 30 to .
be consistent with the original submittal.
Section 14.2.12.1.50 There is no thermal sleeve between CRD housing and drive in accordance with the ABWR design. Therefore, the quoted thermal sleeve installation tool was -
removed from the test item section.
Section 14.2.12.1.51 No change will be made to this item since CUW and RCW are the correct system abbreviations for RWCU and RBCCW respectively per ABWR design terms Section 14.2.12.1.59 Same as response to Section 14.2.12.1.30 comment.
Section 14.2.12.1.61 Yes. The RSW heat exchanger testing has been incorporated into one of the startup phase test item in Section 14.2.12.2.23.
Section 14.2.12.1.62 The quoted test 14.2.12.1.62.(3).(n) was inadvertently added ro the text during typing and will be removed from the text in Amendment 30.
Section 14.2.12.1.64 Yes. The TSW heat axchanger testing has been incorporated into one of the startup phase test item in Section 14.2.12.2.23. l Section 14.2.12.1.67 Same as response to Section 14.2.12.1.30 comment.
Section 14.2.12.1.68 ,
same as response to section 14.2.12.1.30 camment.
Section 14.2.12.1.72 The quoted item 14.2.12.1.72. (3) . (d) . (iv) has been moved to the preceding Jriteria statement of 14.2.12.1.72.(3).(d) for consistency throughout the text.
, 1-a i Response to NRC's Cazment on June 7, 1993 Submittal Startup Test Material
- 1. Page 14.2-129 of 6/7 document i
The quoted words "for those systems incorporated" will be removed from the description section in Amendment 30.
- 2. 14.2.12.2.6 Neutron Monitoring There is no such requirement to calibrate BRNM to indicate actual core thermal power base on (Ae currently existing Technical Specificationa.
However, a requirement to calibrate SRNM and APRM based on a constant heatup rate heat balance calculation during initial heatup will be added to the description section in Amendment 30.
- 3. 14.2.12.2.6 Neutron Monitoring As stated in the response to Itam 2 above, there is no requirement in current Tech Specs to calibrate BRNM to read actual core thermal power.
However, a requirement will be added to description section to ensure SRNM and APRM read reasonable core thermal power during initial heatup.
Both Level 1 and 2 criteria concerning the calibration will be changed -
accordingly in Amendment 30.
- 4. 14.2.12.2.12 As stated in the 14.2.12.1.52 test abstract section, flow testing is to be done during RRS/RPV internal hot functional test at rated volumetric core flow, at rated temperature and pressure conditions without fuels in the core. However, startup phase of reactor internal vibration testing is done with fuel loaded in the core. The flow conditions are different with and without fuels since flow resistance is different between these two cases.
- 5. 14.2.12.2.10 Tho quoted words were inadvertently amitted during typing and will be added to the description section in Amendment 30.
- 6. Table 14.2-1 Ganged rod motion test was moved from OV to HU. With mode switch at REFUEL position during OV phase, it is not allowed to withdraw rods in-ganged groups for demonstration or realignment, if necessary.
Four slowest rods will be determined during full core scram as stated in the text. Full core scrams are required to be performed at HP. Note is misleading and will be revised in Amendment 30.
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SRNM response / calibration test at LP plateau was inadvertently omitted and will be added to Table 14.2-1 in Amendment 30.
Reactor coolant temperature measurements are required in conjunction with RIP trip and restarts and during steady state operation at various power levels. Note is misleading and will be revised in Amendment 30.
Suppression pool cooling can be demonstrated in conjunction with the SRV flow demonstration and operability testing which is scheduled at LP.
Additionally, this test can also be done when test with heat adding to lne suppression pool is being performed as stated in the text. The words "In conjunction with SRV test or after ..." will be added to the note in Amendment 30.
The word " hand" under CUW performance test is a typo and should be " head" instead. However, this word " head" will be deleted from Table 14.2-1 in ,
Amendment 30 to be cor.sistent with the "RPV Spray Mode" statement in the description section.
Turbine trip and load rejection is a correct title for this test. A turbine trip will initiate generator trip and vice versa. A load L rejection (not generator load rejection) at greater than or equal to 40%
of rated thermal power, mismatch between turbine first stage pressure and generator output trips only control valves and intercept valves. Note that turbine is not tripped and generator remains on line in response to this event. :
As stated in the description section of 14.2.12.2.38, a separate radwaste system performance testing is not necessary. Testing specific to the main condenser offgas system is done separately in 14.2.12.2.35. Radiochemical analysis on liquid and gaseous effluents from radwaste system is performed in 14.2.12.2.1. Therefore, 14.2.12.2.38 is a duplicated testing and should be optional.
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