|
---|
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] |
Text
,
r- ! F GE Nuclear Energy ll 170 Cwtw i. cue $sn Jxe (A 95125 May 26,1993 Docket No. STN 52-001 )
i Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation. ,
Subject:
. Submittal Supporting Accelerated ABWR Review Schedule - Composite Changes for Table 3.9-8
Dear Chet:
Enclosed is an SSAR markup of the composite changes to Table 3.9-8 since Amendment 27. :
There have been no changes to Table 3.9-9 since Amendment 27.
a Please provide a copy of this transmittal to Renee Li.
Sincerely, d ,
h -Fox l Advanced Reactor Programs cc: Bernie Genetti (GE) ;
Norman Fletcher (DOE)
+
- I
-l i
020013 i
JVv%1%
i I
9306030076 930506
{DR ADOCK 05200001- "
g
.m- - - - - = - - _ ~
'ABWR mm ;
5ta'ndard Plant g Table 3.9 8 (Continued) ;
IN SERVICE TESTING SAFETY-RELATED PUMPS AND VALVES E11 Residual Heat Removal System Valves (Continued)
Safety Code Valve Test Test SSAR-Class Cet. Func. Para Freq. Fig.
(a) (c) (d) (e) (f) (g) r No. Qty Description (h)(1)
F008 3 Suppression pool reurn line MOV 2 A I,A 1,P- RO 5.4-10(3,4,6)
S 3 mo j F009 3 Shutdown Cooling suct. line maint. viv 1 B P El 5.4-10(2) 7
( F010 3 Shutdown Cooling suct. line inb. iso. viv (h6) 1 A I,A L,P RO 5.4-10(2)
S G
(
Shutdown Cooling suct line outb isc. viv (h6) 1 A I,A 1,P RO 5.4-10(2) l I F011 3 '
S CS
?
Shutdown Cooling suction line adm. viv 2 B A P 2 yrs 5.4-10(3,4,6)
) F012 3 S 3 mo ,
Heat exchanger bypass flow control viv 2 B A P 2 yrs 5.4-10(3,4,6)
F013 3 =
S 3 mo, 2 B A ,S RO 5.4-10(5,7)$p3_progy,.,
Fuel Pool Cooling supply line inb MOV h8)
) F014 2 B A P,S RO 5.4-10(5,7) p.3
~ Fuel Pool Cooling supply line outb MOV 'h8) 2 ., ;
) F015 F016 2 2 Gate viv line from Fuel Pool Clg (FPC) (h8 2 B A (S R 5.4-10(2) g 3hg ;
F017 2 Drywell sprayline inboard valve 2 A I,A 1,P RO 5.4-10(5,7) gg, S 3 mo f
l F018 2 Drywellsprayline outboard valve 2 A I,A 1,P RO 5.4-10(5,7)
S 3 mo Wetwell sprayline MOV 2 A I,A 1,P RO 5.4-10(5,7)
F019 2 S 3 mo
) 3mo 5.4-10(3,4,6)
FU20 3 RHR pump min flow bypass line check viv 2 C A S ,
RHR pump min flow bypassline MOV 2 A I,A 1,P 2 yrs 5.4-10(3,4,6) f F021 3 S 3mo l F022 3 Discharge line fill pump suction line valve 2 B P El 5.4-10(3,4,6) 2 C A' S 3 mo 5.4-10(3,4,6)
F023 3 Fill pump discharge line check valve 2 C A S 3 mo . 5.4-10(3,4,6) ;
F024 3 Fill pump discharge line stop check valve
{ Fih pump minimum flow line globe valve 2 B P El 5.4-10(3,4,6) ,
F025 3 RHR p'unp suction to High Conductivity 2 B P El 5.4-10(3,4,6)
( F026 3
/ Waste (HCW)
F027 3 Bypassline around the check valve 2 B P El 5.4-10(3,4,6)
MPLE11 F002 2 C A R S yrs . 5A-10(3,4,6) .
F028 3 Heat r ' Tr outlet line relicf valve El 5.4 10(3,4,6)'
Inboard reactor well drain line valve 2 B- P .l F029 3 Drain to radwaste valve 2 B P El 5.4-10(3,4,6) .
F030 3
' 2 A I,P . 1,P RO 5.4-10(3,4,6) -
F031 3 Outb reactor well drain line valve (to SP) 2 B P El 5.4-10(3,4,6) .
1 F032 3 Shutoff valve -line from MUWC 2 .C A S 3mo 5.4-10(3,4,6). i F033 3 Check valve in the line from MUWC 4
RPV injection line vent / test line inbd viv 2 B P El 5.410(3)
F034 1 5.4-10(5,7)
F034 2 - RPV injection line vent / test line inbd viv 1 B P El )
i F036 1 Press equal valve around chk viv E11-F006 2 A P El 5.4 10(3) 1 A P E1- 5.4-10(5,7)
Press equal valve around chk viv E11 F006 j F036 2 3.9-58.9 '
Amendment l
i e
4
.ABWR zwi==
Standard Plant n .n Table 3.9-8 (Continued)
IN SERVICE TESTING SAFETY-RELATED PUMPS AND VALVES G31 Reactor Water Cfeanup System Valves (Continued) i Safety Code Valve Test Test SSAR .;
Class Cat- Func. Para Fnq- Fig.. ;
No. Qty Description (h)(1) (a) (c) (d) (e) -(0 (a) ll; F072 1 RPV bottom head drain line sample line 2 A I,A L,P RO 6.4-12(1) f outboard valve S 3mo F500 1 CUW Sys bottom head drain line drain viv 2 B P El 5.4-12(1).
F501 1 CUW Sys bottom head drain line drain viv 2 B P El 5.4-12a 2 B P E1- -!
F700 2 CUW System suction line FE upstream 5.4-12(1) instrument manual @ valve peurTura,re F701 2 CUW System suction line ,FE downstream 2 B P El 5.4-12(1) ,
instrument manual %watumpyalvg.pl,pt,,a F702 2 CUW System suction line FE upstream 2 A,C I,A 1,S,P RO 5.$-12(1) instrument excess flow check valve (h3)
F703 2 CUW System suction line FE downstream 2 A,C I,A L,S,P RO 5.4-12(1) instrument excess flow check valve (h3)
'G41 Fuel Pool Cooling and Cleanup Valves g F015 2 FPC system heat exchanger outlet line 3 B P E1- 9.1-1(2) maintenance valve F016 1 FPC system discharge line to spent fuel 3 C A S 3 mo 9.1-1(2) pool check vahc F017' 1 FPC system discharge line to spent fuel 3 B P El 9.1-1(2) -
pool maintenance valve F018 1 FPC system discharge line to spent fuel 3 C A S 3 mo 9.1-1(2) pool check valve F019 2 FPC system discharge line to spent fuel 3 B P E1 9.11(1),
poolvilve F020 2 FPC system discharge line to spent fuel 3 C .A S 3 mo 9.1-1(1) pool check valve F022 1 FPC system discharge line to reactor well 3 B P E1 9.1-1(2)
==Immmance valve .
F023 1 PFC system discharge line to reactor well 3 C A_ S RO' 9.11(2) cheek valve (h7)
F091 1 FPC system supply line from SPCU check viv 3 C A- S- 3 mo 9.11(2)
F093 1 FPC system RHR return line valve to FPC 3 B P E1 9.11(2)
-F094 1 FPC system RHR return line check valve 3 C A S RO 9.1-1(2) -
to FPC (h7)
F095 1 ' FPC system discharge line to spent fuel 3 B P E1 9.1-1(2) pool sample line F506 1 FPC system line valve from RHR-to-FPC 3 B P El 9.1-1(2) line to LCW
.3.9 58.18 Amendment 23 T _ . - - _ . , _ _ _ , - .
cwFtri (,,2,p 3 y I c. t y MkN 23A6100AE
. ' Standard Plant %a b
Table 3.9-8 (Continued)
IN SERVICE TESTING SAFETY-RELATED PUMPS AND VALVES T22 Standby Gas Treatment System Valves Safety Code Valve Test Test SSAR Class Cat. Func. Para Freq. Fig.
No. Qty Description (h)(1) (a) (c) (d) (e) (r) (g)
F012 2 Filter train DOP samplingline valve 3 B P El 6.5-1(2,3) -
downstream of after HEPA [7 F014 2 STGS sample line valve 3 B P El 6.5-1(2,3)
FD15 2 PRM discharge to stack valve 3 B P El 6.5-1(2,3)
)
F500 2 Filter unit vent line valve 3 B P El 6.5-1(2,3)
F501 2 Filter unit drain line valve 3 B P El 6.5-1(2,3) ,
F504 2 Filter unit vent line valve 3 B P El 6.5-1(2,3) /
F505 2 Exhaust fan vent line valve 3 B P El 6.5-1(2,3) (
F506 2 Filter train vent line valve 3 B P El 6.5-1(2,3) )
F507 2 Futer train vent line valve 3 B P El 6.5-1(2,3) l F508 2 Filter train vent line valve 3 B P El 6.5-1(2,3) ' i F509 2 Fdter train vent line valve 3 B P El 6.5-1(2,3) !
F510 2 Filter train vent line valve 3 B P El 6.5-1(2,3)
F511 2 Exhaust stack drain line valve 3 B P El 6.5-1(2,3)
F700 2 Filter unit demister dp instrument line valve 3 B P El 6.5-1(2,3)
F701 2 Filter unit demister dp instrument line valve 3 B P El 6.5-1(2,3)
F705 2 Filter train prefilter dp instrument line valve 3 B P El 6.5-1(2,3) -
B El 6.5-1(2,3) /
F706 2 Filter train prefilterdp instrument line valve 3 P F707 2 Filter train preHEPA dp instrument line valve 3 B P El 6.5-1(2,3) (
F708 2 Filter train preHEPA dp instrument line valve 3 B P El 6.5-1(2,3)
F709 2 Fliter train charcoal adsorber dp inst. line viv 3 B P El 6.5-1(2,3) l B P El 6.5-1(2,3) 2 F710 2 Filter train charcoal adsorber dp inst line viv 3 F711 2 Filter train after HEPA dp inst line valve 3 B P El 6.5-1(2,3) k F712 2 Filter train after HEPA dp inst line valve 3 B P El 6.5-1(2,3) l F713 2 Filter train exhaust flow instrument line valve 3 B P El 6.5-1(2,3) I F714 2 Filter train exhaust flow instrument line valve 3 B P El 6.5-1(2,3)
T31 Atmospheric Control System Valves (h2)
F001 1 N2 supply line from Reactor Building HVACg 2 A 1,A L,P 2 6.2-39(1)
S & yrsAD l F002 1 N2 supply line to drywell inboard cont- 2 A I,A L,P 2 S @ yrs RO- 6.2-39(1) l ainment isoaltion valve (h 2)
F003 1 N2 supply line to wetwell inboard cont- 2 A 1,A L,P 2 yrs 6.2-39(1) ainment isoaltion valve (A 9) S dRO l F004 1 Containment atmosphere exhaust line from 2 A 1,A L,P 2 6.2-39(1) drywellisoaltion valve (6 2) S @ yrsRD /
F005 1 Drywell atmosphere exhaust line valve 2 A I,A L,P 2 yrs 6.2-39(1)
T31-F004 bypass line S 3 mo _ ;
F006 1 Containment atmosphere exhaat line form 2 A I,A L,P 2 6.2-39(1) l S @ yrsRO l i
werwellisolation valve (A f)
F007 1 Wetwell overpressure line valve 2 A P L.P 2 yrs 6.2-39(1)
Amendment)(
l
CNFrH 6<B5~-3 t'y 2 c f Jf MM Standard Plant DA6100AE wn Table 3.9 8 (Continued) j IN-SERVICE TESTING SAFETY RELATED PUMPS AND VALVES j T31 Atmospheric Control System Valves l Safety Code Valve Test Test SSAR I Class Cat Func. Para Farq. Fig. l No. Qty Description (5)(1) (a) (c) (d) (e) (f) (g) 1 Containment atmosphere exhaust line 2 A 1,A L,P 2 yrs 6.2-39(1) l F008 to SGTS (h f) S M RO 1 Containment atmosphere exhaust line to 2 A 1,A 1,P 2 s 6.2-39(1) l F009 R/B HVAC(h 2)
Drywell overpressure line valve [h 2) 2 A P S
1,P, 3 mo RD 2 yrs 6.2-39(1)
F010 1 y g
- F025 1 N2 supply line from K-5 outboard cont- 2 A 1,A L,P' 2 yrs 6.2-39(1) ainment isolation valve S 3mo F039 1 N2 supplyline from K 5 outboard cont- 2 A 1,A L,P 2 yrs 6.2-39(1) ainment isolation valve S 3 mo FNO 1 N2 supply line from K-5 to drywell inboard 2 A I,A L,P 2 yrs 6.2-39(1) isolation valve S 3 mo F041 1 N2 supply line from K 5 to wetwell inboard 2 A I,A L,P 2 yrs 6.2-39(1) isolation valve S 3 mo F044 8 Drywell/wetwell vacuum breaker valve 2 C A P .RO 6.2-39(2)
R E3 F050 1 N2 supply line to drywell test line valve 2 B P El 6.2 39(1)
F051 1 Containment atmosphere exhaust line test 2 B P El 6.2 39(1) line valve FD54 1 Drywell personnel air lock hatch test 2 B P El 6.2-39(2) line valve FOSS 1 N2 supply line from test line valve 2 B P El 6.2-39(1)
F056 1 Wetwell personnel air lock hatch test 2 B P El 6.2-39(2) line valve F700 1 N2 supplyline to drywell FE upstream 2 B P El 6.2-39(1) instrument line I 101 1 N2 supply line to drywell FE downstream 2 B P El 6.2-39(1) instrument line F702 1 N2 supply line to wetwell FE upstream 2 B P El 6.2-39(1) instrument line F703 1 N2 supplyline to wetwell FE downstream 2 B P El 6.2-39(1) instrument line F720 8 DW/WW vacuum breaker valve N2 supply 2 A I,P L RO 6.2-39(2) line isolation valve F730 1 Drywell pressure instrument line isolation 2 B P El 6.2-39(2) valve F731 1 Drywell pressure instrument line solenoid 2 A 1,P L,P RO 6.2-39(2) isolation valve F732 2 Drywell pressure instrument line valve 2 B P El 6.2-39(2)
F733 2 Drywell presstire instrument line solenoid 2 A 1,P L,P RO 6.2 39(2) isolation vahr .
F734 4 Drywell pressure instrument line for NBS 2 B P El 6.2-39(2) i valve N Foll I den kmrh cit f afmaphere e vInus t 2 A IA' t,P 2ta 6,2 -]9(1) j S RO l x,,.amem p 11ne te SG T5 (h 2) g5a l
q-
'. ABWR 23mman
'. Standard Plant nev. n Table 3.9-8 (Continued)
IN-SERVICE TESTING SAFETY-RELATED PUMPS AND VALVES T31 Atmospheric Control System Valves (Continued)
Safety Code Valve Test Test SSAR Class Cat. Func. Para Freq. Fig.
No. Qty Description (h)(1) (a) (c) (d) (c) (f) (g)
M35 4 Drywell pressure instrument line for NBS 2 A I,P L,P RO 6.2-39(2) solenoid isolation valve F736 2 Wetwell pressure instrument line valve 2 B P El 6.2-39(2)
M37 2 Wetwell pressure instrument line solenoid 2 A I,P L,P RO 6.2-39(2) isolation valve F738 4 Suppression pool water level reference leg 2 B P El 6.2-39(2) instrument line valve F739 4 Suppression pool water level reference leg 2 A I,P L,P RO 6.2-39(2) instrument line solenoid isolation valve F740 4 Suppression pool water level reference leg 2 B P El 6.2-39(2) instrument line valve F741 4 Suppression pool water level reference leg 2 A I,P 1,P RO 6.2-39(2) instrument line solenoid isolation valve F742 2 Suppression pool water level reference leg 2 B P El 6.2-39(2) instrument line valve F743 2 Suppression pool water level reference leg 2 A I,P L,P RO 6.2-39(2) -
instrumes.t line solenoid isolation valve i4744 2 Suppression pool water Icvel 2 B P El 6.2-39(2) instrument line valve F745 2 Suppression pool water level 2 A I,P L,P RO 6.2-39(2) instrument line solenoid {aive ,_,,ffala//en F800 2 Drywell water levelinstrument line 2 B P El 6.2-39(2) reference leg isolation valve F801 2 Drywell water levelinstrument line 2 A I,P L,P RO 6.2-39(2) reference leg solenoid isolation valve F802 2 Drywell water level instrument line valve 2 B P El 6.2 39(2)
F803 2 Drywell water level instrumewnt line solenoid 2 A I,P L,P RO 6.2-39(2) isolation vaht F804 2 DW/WW differential pressure instrument 2 B P El 6.2-39(2) line valve F805 2 DW/WW diffrential pressure instrument 2 A I,P L,P RO 6.2-39(2) solenoid isolation vaht D001 1 Wetwell overpressure rupture disk 2 I,D P Rplc. 5 yrs 6.2-39(1)
D002 1 Drywell overpressure rupture disk 2 1,D P Rplc. 5 yrs 6.2-39(1)
T49 FIhmmability Control System Valves 1 F001 2 Inlet line from drywellinboard 2 A I,A L,P 2 yrs 6.2-40 isolation valve S 3 mo F002 2 Inlet line from drywell cutboard 2 A I,A L,P 2>Ts 6.2-40 isolation valve S 3 mo 3.9-58.29 Amendmentf
j - g; g' }
i
' ~
MkN 23A3100AE Standard Plant , , , ,
Table 3.9 8 (Continued)
IN. SERVICE TESTING SAFETY RELATED PUMPS AND VALVES NOTES (Continued):
(g) Piping and instrument syrnbols and abbreviations are defined in Figure 1.7-1. Figure page numbers are shown in parenthesis ().
(h) Reasons for code defined testing exceptions (Part 10, Paragraphs 4.2.1.2 and 4.3.2.2). p (hl) Inaccessible inerted containment and/or steam tunnel radiation during power operations.
(h2) Avoids valve damage and impacts on power operations.
(h3) Avoids impacts on power operations.
(h4) A temporary crosstie is necessary to carry the ongoing cooling loads. A permanent crosstic would (
violate divisional separation. $
(h5) Avoids cold / hot water injection to RPV during power operations.
(h6) Maintain pressure isolation during normal operation.
(h7) Inventory available only during refueling outage.
Mefd' (h8) esting at power will impact operation because the valves do not automatically isolate with p ,
CA signal - )
l (h9) Test connection size is insufficient for full flow test during operation. Therefcre, test part stroke during plant operation and full stroke during refueling outage. A test connection size which would /
be sufficient for full flow tests would pressurize the secondary containment beyond specified "
limits, thus affecting power operation.
/
Summary justification for code exemption request (Part 6, Paragraph 5.2, or Part 10, Paragraph 6.2). ;
(i)
(ii) The piping is maintained full by a small fraction of the pump's flow capacity. These pumps may ,
be a constant speed centrifugal type with a cooling by-pass loop. Normal operation will be near minimum flow in the flat or constant region of the pressure / flow performance curve. Therefore, ,
a flow measurement would not be useful. The pumps will be designed and analyzed to withstand j low flow operation without significant degradation.
a gggg 3.h -