|
|---|
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: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
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
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
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
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
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
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
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
ML20070D9331994-05-26026 May 1994
Forwards Results of Analyses to Assess Impact of Drywell Spray Actuation Following LOCA to Ensure Bounding Scenario
ML20069B1831994-05-25025 May 1994
Resubmits Affidavit for GE Abwr,Proprietary Info Section 18H, Supporting Analysis for Emergency Control Operation Info
ML20069G9301994-05-25025 May 1994
Submits non-proprietary SSAR Amend 35 & Certified Design Material Rev 4 to Listed NRR Recipients
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
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
_ _.
GENuclexrEnergy Genera! Electric company.
175 Curtner Avenue. S?n Jose, CA 95125 l
i May 7,1993 36cket No. STN 52-001 f
l t
t i
Chet Poslusny, Senior Project Manager j
Standardization Project Directorate '
Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation I
t
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - DFSER Confirmatory item 6.2.5-3
Dear Chet:
Enclosed is a SSAR markup addressing DFSER Confirmatory Item 6.2.5-3 which supplements i
my letter dated March 3,1993.
I Please provide a copy of this transmittal to Butch Burton.
Sincerely, i
Y A
i
, ack Fox i
Advanced Reactor Programs I
cc: Norman Fletcher (DOE) i Bernie Genetti(GE) q i
i i
JF93-D9
- 9305130017 930507 7
PDR. ADOCK 05200001 '
A
- PDR
C' W F tr1 (,,2. p. 3 y) of y
\\
23A6100AE Standard Plant
%n Table 3.9-8 (Continued)
)
IN-SERVICE TESTING SAFETY-REIATED 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)
(f)
(g)
F012 2 Fdter train DOP sampling line 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)
F015 2 PRM discharge to stack valve 3
B P
El 6.5-1(2,3)
)
F500 2 Filter unit vent 1;ne 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 63-1(2,3) i F505 2 Exhaust fan vent line valve 3
B P
El 6.5-1(2,3)
F506 2 Fdter train vent line valve 3
B P
El 6.5-1(2,3)
F507 2 Futer train vent line valve 3
B P
El 65-1(2,3)
(
Ff98 2 Filter train vent line valve 3
B P
El 65-1(2,3)'
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 65-1(2,3)
F511 2 Exhaust stack drain line valve 3
B P
El 65-1(2,3)
F700 2 Fdter 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 Fdter train prefilter dp instrument line valve 3
B P
El 6.5-1(2,3)
F706 2 Filter train prefilterdp instrument line valve 3
B P
El 6.5-1(2,3)
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 F710 2 Filter train charcoal adsorber dp inst line viv 3
B P
El 6.5-1(2,3).
/
F711 2 Filter train after HEPA dp inst line valve 3
B P
El 63-1(2,3) b i
F712 2 Fdter train after HEPA dp inst line valve 3
B P
El 6.5-1(2,3) 1 I
F713 2 Fiher train exhaust flow instrument line valve 3 B
P El 6.5-1(2,3)
F714 2 Fdter train exhaust flow instrument line valve 3 B
P El 65-1(2,3)
T31 Atmospheric Control System Valves (h2),
2 6.2 39(1) t A
1,A L,P F001 1 N2 supply line from Reactor Building HVACg
& yrsRD l
S 2
6.2-39(1)
F002 1 N2 supply line to drywell inboard cont-2 A
1,A 1,P
@>Ts RO
(
ainment isoaltion valve [h 2)
S F003 1 N2 supply line to wetwell inboard cont-2 A
1,A L,P 2 yrs 6.2-39(1) ainment isoaltion valve (/, 2)
S
@$RO l
2 6.2-39(1)
F004 1 Containment atmosphere exhaust line from -
2 A
1,A 1,P
@ yrsRD
/
drywellisoaltion valvefh 2]
S F005 1 Drywell atmosphere exhaust line valve 2
A 1,A 1,P 2 yrs 6.2-39(1)
S 3 mo T31-FD04 bypass line F006 1 Containment atmosphere exhaust line form 2
A 1,A L,P 2 yrs 6.2-39(1) wetwellisolation valve (6 f)
S QRO l
F007 1 Wetwell overpressure line valve 2
A P
L,P 2 yrs 6.2-39(1) 3.9 5827-Amendment)(
a
~
enin sa.s.3 ep p
. gg 23A6100AE Standard Plant wa Table 3.9-8 (Continued)
IN-SERVICE TESTING SAFETY-RELATED PUMPS AND VALVES T31 Atmospheric Control System Valves Safety Code Valve Test Test SSAR Class Cat. Fune. Para Farq. Fig..
No-Qty Description (h)(1)
(a)
(c)
(d)
(e)
(r)
(g) 1 Containment atmosphere exhaust line 2
A I,A L,P di$go.2-39(1) 2 yrs 6 l F008 to SOTS (h t)
S 1
Containment atmosphere exhaust line to 2
A I,A L,P 2
6.2-39(1) l F009 R/B HVAC(h 2)
, A P
L,P 2 yrs 6.2-39(1)
S m
RO F010 1 Drywelloverpressure line valve 2
NF025 1 N2 supply line from K-5 outboard cont-2 A
I,A L,P 2 yrs 6.2-39(1) ainment isolation valve S
3 mo FD39 1 N2 supply line from K 5 outboard cont-2 A
I,A L,P 2yis 6.2-39(1) ainment isolation valve S
3mo F040 1 N2 supply line from K 5 to drywellinboard 2
A I,A L,P 2 yrs 6.2-39(1) isolation valve S
3mo 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
3mo 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
E1.
6.2-39(1)
FD51 1 Cor.tainment atmosphere exhaust line test 2
B P
El 6.2-39(1) line valve F054 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) instru: nest line F701 1 N2 supply line to drywell FE downstream 2
B P
El 6.2-39(1) instrument line F702 1 N2 supplyline to wetwell FE upstream 2
B P
El 6.2-39(1) instrument line F703 1 N2 supply line to wetwell FE downstream 2
B P
El 6.2-39(1) mstrument line F720 8 DW/WW vacuum breaker valve N2 supply 2
A I,P L
RO 6.2-39(2) lineisolation 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 I,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 pressure instrument line solenoid 2
A I,P L,P RO 6 2-39(2) isolation valve F734 4 Drywell pressure instrument line for NBS 2
B P
.El 6.2 39(2) valve N Poil I Johe co SG TS (h 2)yhe,e ohnst eimfaineheirf rhm 2
A IA L,P
.2 W1 6.2-]q(s)
S RO 3,
ue,e emp
CNFm 6
^
~
ggig
- Rev c Standard Plant (16) The primary containment purge system will required, through a pathway from the wetwell l
aid in the long-term post-accident cleanup airspace to the stack. The pathway is isolated operation. The primary containment during normal operation with two rupture disks.
-l atmosphere will be purged through the SGTS ge$
l to the outside environment. Nitrogen makeup The following modes of operation are provided:
f will be available during the purging operation.
(1) Startup - Inerting. Liquid nitrogen is j
vaporized with steam or electric heaters to (17) The system is also designed to release a temperature greater than 200F and is containment pressure before uncontrolled injected into the wetwell and the drywell.
i containment failure could occur.
The nitrogen will be mixed with the primary containment atmosphere by the drywell j
6.2.5.2 System Design coolers in the drywell and, if necessary, by the sprays in the wetwell.
I 6.2.5.2.1 General (2) Normal - Maintenance of Inert Condition. A l
The ACS provides control over hydrogen and nitrogen makeup system automatically sup-oxygen generated following a LOCA. In an inerted plies nitrogen to the wetwell and upper f
containment, mixing of any hydrogen generated is drywell to maintain a slightly positive not required. Any oxygen evolution from pressure in the drywell and wetwell to pre-l radiolysis is very slow such that natural clude air leakage from the secondary to the l
convection and molecular diffusion is sufficient primary containment. An increase in con-l to provide mixing. Spray operation will provide -
tai ament pressure is controlled by venting (2}
furth:r assurance that the drywell or wetwell is through the drywell bleed line.
uniformly mixed. The system consists of the l
following features:
(3) Shutdown - Deinerting. Air is provided to the drywell and wetwell by the primary j
(1) Atmospheric mixing is achieved by natural containment HVAC purge supply fanc Exhaust processes. Mixing will be enhanced by is through the' drywell, exhaust lines and utA j
operation of the containment sprays, which Mwetwelpto the plant vent, through the H\\
L or SGT as required. sustar A I
1 are used to control pressure in the primary
. c1hnsf)Iarts l
containment.
(4) Overpressure Protection. If the wetwell.
l (2) The piimary containment nitrogen purge pressure increases to about 5.6
)
2 establishes and maintains an oxygen -
kg/cm g. the rupture disks will open.
deficient atmosphere (13.$ volume percent)
The overall containment pressure decreases in the primary containment during normal as venting continues. Later, the operators operation.
can close the two 350A air-operated j
butterfly valves to re-establish j
(3) The redundant oxygen analyzer system (CAMS) containment isolation as required.
measures oxygen in the drywell and suppression chamber. Oxygen concentration The following interfaces with other systems are displayed in the main control room, are provided:
Description of safety-related display instrumentation for containment monitoring (1) Residual Heat Removal System (RHR-Ell),
is provi,ded in Chapter 7.
Electrical.
The RHR provides post-accident suppression requirements for equipment associated with pool cooling as necessary_ following heat the combustible gas control system are in dumps to the pool, including the exothermic accordance with the appropriate IEEE heat of reaction released by the design.
standards as referenced in Chapter 7.
basis metal-water reaction. This heat of reaction is very small and has no real In addition, the ACS provides overpressure affect on pool temperature or RHR heat' protection to relieve containment pressure, as exchanger sizing. The wetwell spray IW5 W A
)
Ammendment[
9uRIVq Clwldmson f Uqe -W povIdes c$$31nmed acces/
}
6.2-33 Ven H la fion.
I i
.=-.-.
-.w
i enn u.m y n ABWR
~
Standard Plant REV C l
differentials and flow rates, are documented monitored. Low makeup vaporizer nitrogen outlet during the preoperational tests and are used as temperature alarms (only) in the main control Auxiliary steam feeding the main inerting base points for measurements in subsequent room.
operational tests.
vaporizer (s) is controlled to regulate the inerting vaporizer nitrogen outlet temper -
During plant operation, the ACS, its valves, ature. Low inerting vaporizer nitrogen outlet instrumentation, wiring and other components temperature sounds a local alarm and low low outside the containment can be inspected visually temperature isolates the main inerting line. It at any time. Testing frequencies of the ACS com-is intended that the local panel be attended ponents aie generally correlated with testing full-time during all main inerting operations.
frequencies of the associated controls and in-All locally-mounted instruments are easily read strumentation. When a valve control is tested, from the local ACS panel. Keylocked switches in the operability of that valve and its associated the main control room are provided to override instrumentation are generally tested by the same the containment isolation signal to the valves action. In addition, inservice inspectiongf all providing nitrogen makeup to the drywell and and ASME, Section 111, Class 3 com nents is done in wetwell and the small 50 mm drywell vent line. I
- "7 accordance with Subsection 6.6.
cyng 7.</4 Position indication in the main control room is respectheh, provided for all remotely-operated valves.
f Preoperational tests of the combustible gas control system are conducted during the final Backup purge and the addition of makeup stages of plant construction prior to initial nitrogen is initiated at t he oper ator's startup.
discretion.
The overpressure protection concept was Design d e t ails and logic of the designed to minimize any adverse impact on normal instrumentation is discussed in Chapter 7.
operation or maintenance. Initially, several rupture disks from a batch of rupture disks could As discussed in Section 6.2.5.2, safety-grade be tested to verify the opening characteristics oxygen monitoring is provided in the wetwell and and setpoint. The disks would be replaced every drywell by the CAMS. This monitoring function five years according to normal industry practice. is not used for normal operation. Separate The installation of the disks would not impact oxygen monitoring is included in the ACS for use containment leakage tests, since disk integrity is during non accident plant operation to determine expected to be essentially perfect.
when the primary containment is inert and nitrogen purging may be terminated and when the The rnerprenue protection valves would be primery containment is de inened a::d pencenel tested during preoperational testing and re-entry procedures may be initiated.
periodically during surveillance testing to verify their normally open position and their ability to The ACS oxygen monitors for assuring safe close using AC power and pneumatic air.
personnel entry and an inert condition during startup, normal, and abnormal operating 6.2.5.5 Instrumentation Requirements conditions have a range from 0 to 25 percent at 100 percent relative humidity. The maximum and Separate inerting flow indication to both the minimum inlet temperature to the oxygen monitor drywell and wetwell are provided. Drywell will be 10 and 650C, respectively. Two sample pressure and makeup flow are monitored and points are provided in both the drywell and recorded in the main control room. Additional wetwell, high and low in their respective drywell pressure instrumentation, with a lower compartments and in opposing quadrants. Each setpoint, provided in addition to the redundant, airlock is also sampled.
safety-grade drywell pressure instrumentation of i
the nuclear boiler system, if drywell pressure The sample lines are sized and sloped to exceeds a given setpoint, the makeup and inerting assure draining condensation to the containment.
i valves are closed. The temperature of the makeup and inerting vaporizers nitrogen outlet are Amendmem[
U