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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073T0701994-07-0101 July 1994 Reports Changes & Errors in ECCS Evaluation Models ML20090J9651992-03-11011 March 1992 Forwards Piping Design Insps,Tests,Analysis & Acceptance Criteria (Itaac).Piping Design ITAAC Will Be Included as Part of Generic ITAAC ML20090J9701992-03-11011 March 1992 Forwards Proprietary Responses to Issues Re Sections 9.3,9.5 & 11.2 of Advanced BWR Ssar.Responses Reflect Correctons & Additions to Earlier Proprietary Submittals.Responses Withheld ML20090J9791992-03-11011 March 1992 Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355) ML20090J9941992-03-11011 March 1992 Forwards Draft Rev 0 to Advanced BWR Srvdl Wetwell Piping Stress Analysis Design Rept & Draft Rev 0 to Design Rept, Main Steam Line a & Safety Relief Valve Discharge Piping Stress Analysis, Per 911209-10 Ge/Nrc Meeting ML20090G5801992-03-0909 March 1992 Summerizes Staff Position Re NRC Conference Call on Dser Comments to Advanced BWR Ssar ISI Requirements ML20090F6171992-03-0505 March 1992 Forwards Rev B to 23A6100AQ,Section 17.3 Re Responses to Request for Resolution of Issues Related to Reliability Assurance Program (Rap).Subj Responses Will Be Included as Amend to Advanced BWR Ssar in Future ML20094G9691992-03-0202 March 1992 Forwards Radwaste Bldg Seismic Analysis. Informs That GE Intends to Amend Ssar W/Subj Analysis in Future Amend ML20094G7141992-02-25025 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092N1451992-02-25025 February 1992 Requests Addition of Listed Individual to Advanced BWR Document Distribution List ML20094G7401992-02-25025 February 1992 Forwards Proprietary Summary of 920127 Telcon W/Nrc & Brookhaven Lab to Clarify Aspects of Human Factors Review of Advanced Bwr,Specifically Review of Design Implementation Process.Summary Withheld ML20090A0441992-02-25025 February 1992 Forwards Proprietary Rev R-0 to Advanced BWR Project Common Engineering Work Plan. Plan Withheld ML20092L0801992-02-25025 February 1992 Forwards App 19P to Chapter 19 of Evaluation of Potential Mods to Advanced BWR Design ML20090B1881992-02-24024 February 1992 Forwards Draft Rev 0 to Advanced BWR Ssar Main Steam, Feedwater & Srvdl Piping Sys Design Criteria & Analysis Methods & Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads, Per Ge/Nrc 911209-10 Meeting ML20092M2931992-02-20020 February 1992 Forwards Discussion of Differences Between Us Advanced BWR & K-6/7 Project.Advanced BWR Design Under Review for for Differences to K 6/7 & Addl Differences Will Be Included in Future Ssar Amend ML20094G7201992-02-17017 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092F4241992-02-14014 February 1992 Forwards Proprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch. Response Withheld ML20092F4601992-02-14014 February 1992 Forwards Nonproprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch Re Standby Liquid Control Sys Instrumentation & Controls ML20092F4971992-02-13013 February 1992 Forwards Proprietary App 18F, Emergency Operation Info & Controls to Chapter 18, Human Factors Engineering of Advanced BWR Std SAR Covering Control Room Inventory.App 18F Withheld ML20092F5251992-02-11011 February 1992 Responds to Performance & Quality Evaluation Branch Open Items on Advanced BWR Std SAR Chapter 14 ML20092F5181992-02-10010 February 1992 Forwards Responses to 920110-16 Requests for Addl Info on Advanced BWR Design for Severe Accidents ML20092C0251992-02-0303 February 1992 Forwards Proprietary Responses to Addl Info Noted in 911004 Draft SER for Chapter 7.Responses Are Cross Ref W/Summary Item Number Corresponding to Review Meeting in San Jose on 910807 & 08.Responses Withheld ML20092C1671992-02-0303 February 1992 Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR Ssar W/Responses in Future Amend ML20092C1831992-02-0303 February 1992 Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend Ssar W/Response in Future Amend ML20100P9651992-01-31031 January 1992 Forwards Proprietary NEDC-30032 Joint Study Final Rept - Joint Study W/Regard to 'Study (II) Related to Advanced Bwr' - Thermal Margin During Rapid Coastdown,820401-830331. Rept Withheld ML20091K8911992-01-22022 January 1992 Forwards Response to Open Issue 3 of SECY-91-153 Re Main Steam Line Seismic Classification Including,Static Design Procedure to Be Utilized in Evaluation of Seismic Capability of Condenser Anchorage & Turbine Bldg ML20094E4571992-01-17017 January 1992 Forwards Tier 1 Design Certification Matl,Pilot Itacc Examples for GE Advanced BWR Design & Advanced BWR Design Certification Generic ITAAC for Seismic Category 1 Structures,Position Paper ML20087D2641992-01-10010 January 1992 Forwards Response to Agenda Items 1,5,9 & 16 Discussed at Ge/Nrc Reactor Sys Branch 911120-21 Meetings.Items Include, Stability Performance in Normal Operating Region,Loss of Ac Power & Loss of Feedwater Heating Transient ML20087D4771992-01-10010 January 1992 Forwards Responses to Agenda Item 12 Discussed During 911120-21 Meeting W/Reactor Sys Branch of Nrc.Responses Withheld ML20087D0011992-01-0606 January 1992 Forwards Proprietary Tables to App 18F to Chapter 18 Re Human Factors Engineering.Ge Will Amend Ssar to Include Subj Info in Future Amend.Encl Withheld ML20087B7161992-01-0606 January 1992 Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld ML20086U5451992-01-0606 January 1992 Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR ML20086U1941991-12-20020 December 1991 Confirms That Licensee Advanced BWR Application Should Be Processed as Application for Part 52 Final Design Approval & Subsequent Design Certification Per 10CFR52.45 ML20086N9601991-12-19019 December 1991 Forwards Proprietary & Nonproprietary Versions of Rev B to Update of App 9A, Reactor Bldg Fire Hazard Analysis ML20086P2161991-12-19019 December 1991 Forwards Proprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086P2251991-12-19019 December 1991 Forwards Nonproprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20091H4061991-12-13013 December 1991 Forwards Selected Sections of Chapter 9, Auxiliary Sys & Chapter 18, Human Factors Engineering of Ssar for Advanced Bwr,Amend 19,including Update of Control Bldg Fire Protection Drawings.Encl Withheld ML20086N2161991-12-13013 December 1991 Forwards Amend 19 to Advanced BWR Ssar ML20094D2041991-12-12012 December 1991 Forwards Proposed Advanced BWR Tech Specs,Per Vendor to Nrc.Specs Will Be Documented Via Amend to Chapter 16 of Advanced BWR Ssar,Once Specs Finalized ML20086H5741991-12-0202 December 1991 Describes Plan for Submitting Advanced BWR Tech Specs to Nrc,Per 911108 Meeting.First Submittal of Noninstrumentation & Control Sys Will Be Submitted by 911213.Third Submittal Re 65 Unchanged LCOs Will Be Submitted by 920131 ML20086H6101991-11-27027 November 1991 Forwards Responses to Open Issues in GE Advanced BWR Ssar Chapter 8 Re Offsite Power Sys & Protective Sys for Reactor Internal Pumps,Per 910916-18 Meeting W/Nrc.Proprietary Versions of Response Withheld ML20086H6161991-11-27027 November 1991 Forwards Proprietary Responses to Open Issues 8.3.3.6 & 8.3.5 for Advanced BWR Ssar,Chapter 8,per Commitment at 910916-18 Meeting in San Jose.Encl Withheld ML20086E4831991-11-25025 November 1991 Forwards Tables Re Significant New Open Issues Included in Final,Draft Ser,Significant Open Items Included in All Draft Sers,Ge Future Submittals & Proposed Issues for Discussion at Dec Mgt Meeting,Per NRC ML20086C7201991-11-12012 November 1991 Forwards Proprietary Draft Writeup for Fire Protection PRA, as Requested in Draft SER on Advanced BWR Pra,Per SECY-91-309,dtd 911001.Encl Withheld ML20086A8121991-11-12012 November 1991 Forwards Draft Writeup for Fire Protection Probabilistic Risk Assessment Requested in Draft SER on Advanced BWR Probabilistic Risk Assessment.Ge Will Amend Ssar to Include Info When Finalized ML20079P1731991-11-0707 November 1991 Forwards Response to Discussion Item 7 from 910906 Conference Call Re Rod Block Algorithm & Setpoint ML20079L7461991-11-0101 November 1991 Forwards Summary of Major Advanced BWR Design Differences, Assessment of How TS Differ from Improved Ts,Including Summary of New,Different or Inapplicable & Example of How TS Would Be Written Where TS Differ from Improved TS ML20079M2561991-11-0101 November 1991 Forwards Proprietary GE Responses to Staff Position Re GE BWR Power Upgrade Program,Dtd 910930.Responses in Ref to Licensing Topical Rept NEDC-31897P-1, Generic Evaluations of GE BWR Power Uprate,June 1991. Responses Withheld ML20079L3121991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 ML20058L6811991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 1994-07-01
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20073T0701994-07-0101 July 1994 Reports Changes & Errors in ECCS Evaluation Models ML20090J9651992-03-11011 March 1992 Forwards Piping Design Insps,Tests,Analysis & Acceptance Criteria (Itaac).Piping Design ITAAC Will Be Included as Part of Generic ITAAC ML20090J9701992-03-11011 March 1992 Forwards Proprietary Responses to Issues Re Sections 9.3,9.5 & 11.2 of Advanced BWR Ssar.Responses Reflect Correctons & Additions to Earlier Proprietary Submittals.Responses Withheld ML20090J9791992-03-11011 March 1992 Forwards Responses to Resolution of Issues Related to Advanced BWR Draft SER Chapters 1,2,3,5,6,9,10,12,13,14 & 15 (SECY-91-355) ML20090J9941992-03-11011 March 1992 Forwards Draft Rev 0 to Advanced BWR Srvdl Wetwell Piping Stress Analysis Design Rept & Draft Rev 0 to Design Rept, Main Steam Line a & Safety Relief Valve Discharge Piping Stress Analysis, Per 911209-10 Ge/Nrc Meeting ML20090G5801992-03-0909 March 1992 Summerizes Staff Position Re NRC Conference Call on Dser Comments to Advanced BWR Ssar ISI Requirements ML20090F6171992-03-0505 March 1992 Forwards Rev B to 23A6100AQ,Section 17.3 Re Responses to Request for Resolution of Issues Related to Reliability Assurance Program (Rap).Subj Responses Will Be Included as Amend to Advanced BWR Ssar in Future ML20094G9691992-03-0202 March 1992 Forwards Radwaste Bldg Seismic Analysis. Informs That GE Intends to Amend Ssar W/Subj Analysis in Future Amend ML20094G7401992-02-25025 February 1992 Forwards Proprietary Summary of 920127 Telcon W/Nrc & Brookhaven Lab to Clarify Aspects of Human Factors Review of Advanced Bwr,Specifically Review of Design Implementation Process.Summary Withheld ML20090A0441992-02-25025 February 1992 Forwards Proprietary Rev R-0 to Advanced BWR Project Common Engineering Work Plan. Plan Withheld ML20094G7141992-02-25025 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092N1451992-02-25025 February 1992 Requests Addition of Listed Individual to Advanced BWR Document Distribution List ML20092L0801992-02-25025 February 1992 Forwards App 19P to Chapter 19 of Evaluation of Potential Mods to Advanced BWR Design ML20090B1881992-02-24024 February 1992 Forwards Draft Rev 0 to Advanced BWR Ssar Main Steam, Feedwater & Srvdl Piping Sys Design Criteria & Analysis Methods & Draft Rev 0 to Advanced BWR Feedwater Loop a Piping & Equipment Loads, Per Ge/Nrc 911209-10 Meeting ML20092M2931992-02-20020 February 1992 Forwards Discussion of Differences Between Us Advanced BWR & K-6/7 Project.Advanced BWR Design Under Review for for Differences to K 6/7 & Addl Differences Will Be Included in Future Ssar Amend ML20094G7201992-02-17017 February 1992 Forwards Proprietary Revised App 18E, Advanced BWR Man-Machine Interface Sys Design & Implementation Process, of Advanced BWR Ssar.App Withheld ML20092F4241992-02-14014 February 1992 Forwards Proprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch. Response Withheld ML20092F4601992-02-14014 February 1992 Forwards Nonproprietary Portion of GE Response to Agenda Items Discussed During 911120-21 Meeting W/Nrc Reactor Sys Branch Re Standby Liquid Control Sys Instrumentation & Controls ML20092F4971992-02-13013 February 1992 Forwards Proprietary App 18F, Emergency Operation Info & Controls to Chapter 18, Human Factors Engineering of Advanced BWR Std SAR Covering Control Room Inventory.App 18F Withheld ML20092F5251992-02-11011 February 1992 Responds to Performance & Quality Evaluation Branch Open Items on Advanced BWR Std SAR Chapter 14 ML20092F5181992-02-10010 February 1992 Forwards Responses to 920110-16 Requests for Addl Info on Advanced BWR Design for Severe Accidents ML20092C0251992-02-0303 February 1992 Forwards Proprietary Responses to Addl Info Noted in 911004 Draft SER for Chapter 7.Responses Are Cross Ref W/Summary Item Number Corresponding to Review Meeting in San Jose on 910807 & 08.Responses Withheld ML20092C1671992-02-0303 February 1992 Forwards Nonproprietary Responses to Addl Items of Concern Noted in Draft SER for Chapter 7.Advises That GE Will Amend Advanced BWR Ssar W/Responses in Future Amend ML20092C1831992-02-0303 February 1992 Forwards Response to Leak Before Break Issue Addressed in 911209-10 Ge/Nrc Meeting.Advises That GE Intend to Amend Ssar W/Response in Future Amend ML20100P9651992-01-31031 January 1992 Forwards Proprietary NEDC-30032 Joint Study Final Rept - Joint Study W/Regard to 'Study (II) Related to Advanced Bwr' - Thermal Margin During Rapid Coastdown,820401-830331. Rept Withheld ML20091K8911992-01-22022 January 1992 Forwards Response to Open Issue 3 of SECY-91-153 Re Main Steam Line Seismic Classification Including,Static Design Procedure to Be Utilized in Evaluation of Seismic Capability of Condenser Anchorage & Turbine Bldg ML20094E4571992-01-17017 January 1992 Forwards Tier 1 Design Certification Matl,Pilot Itacc Examples for GE Advanced BWR Design & Advanced BWR Design Certification Generic ITAAC for Seismic Category 1 Structures,Position Paper ML20087D2641992-01-10010 January 1992 Forwards Response to Agenda Items 1,5,9 & 16 Discussed at Ge/Nrc Reactor Sys Branch 911120-21 Meetings.Items Include, Stability Performance in Normal Operating Region,Loss of Ac Power & Loss of Feedwater Heating Transient ML20087D4771992-01-10010 January 1992 Forwards Responses to Agenda Item 12 Discussed During 911120-21 Meeting W/Reactor Sys Branch of Nrc.Responses Withheld ML20087D0011992-01-0606 January 1992 Forwards Proprietary Tables to App 18F to Chapter 18 Re Human Factors Engineering.Ge Will Amend Ssar to Include Subj Info in Future Amend.Encl Withheld ML20087B7161992-01-0606 January 1992 Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld ML20086U5451992-01-0606 January 1992 Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR ML20086U1941991-12-20020 December 1991 Confirms That Licensee Advanced BWR Application Should Be Processed as Application for Part 52 Final Design Approval & Subsequent Design Certification Per 10CFR52.45 ML20086N9601991-12-19019 December 1991 Forwards Proprietary & Nonproprietary Versions of Rev B to Update of App 9A, Reactor Bldg Fire Hazard Analysis ML20086P2251991-12-19019 December 1991 Forwards Nonproprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20086P2161991-12-19019 December 1991 Forwards Proprietary Responses to Resolution of Issues Re Advanced BWR Draft SER ML20091H4061991-12-13013 December 1991 Forwards Selected Sections of Chapter 9, Auxiliary Sys & Chapter 18, Human Factors Engineering of Ssar for Advanced Bwr,Amend 19,including Update of Control Bldg Fire Protection Drawings.Encl Withheld ML20086N2161991-12-13013 December 1991 Forwards Amend 19 to Advanced BWR Ssar ML20094D2041991-12-12012 December 1991 Forwards Proposed Advanced BWR Tech Specs,Per Vendor to Nrc.Specs Will Be Documented Via Amend to Chapter 16 of Advanced BWR Ssar,Once Specs Finalized ML20086H5741991-12-0202 December 1991 Describes Plan for Submitting Advanced BWR Tech Specs to Nrc,Per 911108 Meeting.First Submittal of Noninstrumentation & Control Sys Will Be Submitted by 911213.Third Submittal Re 65 Unchanged LCOs Will Be Submitted by 920131 ML20086H6161991-11-27027 November 1991 Forwards Proprietary Responses to Open Issues 8.3.3.6 & 8.3.5 for Advanced BWR Ssar,Chapter 8,per Commitment at 910916-18 Meeting in San Jose.Encl Withheld ML20086H6101991-11-27027 November 1991 Forwards Responses to Open Issues in GE Advanced BWR Ssar Chapter 8 Re Offsite Power Sys & Protective Sys for Reactor Internal Pumps,Per 910916-18 Meeting W/Nrc.Proprietary Versions of Response Withheld ML20086E4831991-11-25025 November 1991 Forwards Tables Re Significant New Open Issues Included in Final,Draft Ser,Significant Open Items Included in All Draft Sers,Ge Future Submittals & Proposed Issues for Discussion at Dec Mgt Meeting,Per NRC ML20086C7201991-11-12012 November 1991 Forwards Proprietary Draft Writeup for Fire Protection PRA, as Requested in Draft SER on Advanced BWR Pra,Per SECY-91-309,dtd 911001.Encl Withheld ML20086A8121991-11-12012 November 1991 Forwards Draft Writeup for Fire Protection Probabilistic Risk Assessment Requested in Draft SER on Advanced BWR Probabilistic Risk Assessment.Ge Will Amend Ssar to Include Info When Finalized ML20079P1731991-11-0707 November 1991 Forwards Response to Discussion Item 7 from 910906 Conference Call Re Rod Block Algorithm & Setpoint ML20079M2561991-11-0101 November 1991 Forwards Proprietary GE Responses to Staff Position Re GE BWR Power Upgrade Program,Dtd 910930.Responses in Ref to Licensing Topical Rept NEDC-31897P-1, Generic Evaluations of GE BWR Power Uprate,June 1991. Responses Withheld ML20079L7461991-11-0101 November 1991 Forwards Summary of Major Advanced BWR Design Differences, Assessment of How TS Differ from Improved Ts,Including Summary of New,Different or Inapplicable & Example of How TS Would Be Written Where TS Differ from Improved TS ML20079L3121991-10-25025 October 1991 Forwards Rept Providing Update of in-reactor Surveillance Programs & Overall GE BWR Fuel Experience Through Dec 1990 ML20085K2631991-10-25025 October 1991 Forwards Addl Documents,In Response to NRC Re Resolution of Issues Related to Chapter 18 of Ssar for Advanced BWR Design.Documents Withheld 1994-07-01
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4 CE Nuclear Energy November 7,1991 hiFN No.142 91 DocLet No. STN SNiO5 EEN 9179 Document Control Desk U.S. Nuclear Regulatory Comrnission Washington, D.C. 20555 Attention: itobert C. Pierson, Director Standardiration and Non.I'ower iteactor Project Directorate
Subject:
GE Response to GE/NRC Reactor Splem tiranch Conference Call of September 6,1991 Enclosed are thirty four (34) copies of the GE responses to Discussion item 7 (pertaining to rod block algorithm and set point) of the subject call.
It is intended that GE will incorporate this response in a future amendment.
Sinees ely, s
P.W. Marriott, Manager
- Regulatory and Analysis Services M/C 382, (408) 925 6948 -
ec: F. A. Ross (DOE)
N. D. Fletcher (DOE)
C. Poslusny, Jr. (NRC)
R. C. llerglund (GE) g J. F. Quirk (GE)
\u,\
9111120264 911107 PDR ADOCK 0500060L A PDR
- .- ... - . -.- ~ - - - , _ .. . -. . . - . . . . . . , - . - . . - - , . . - - - , , _ ~
.ABWR -r Slin_dard Plant Rrv n two channel operability. The operator has scram time performance based on the scram the capability to invoke bypass conditions timing data received from the RC&lS.
within the following system or subsystems: g gyggg A 7.7.1.2.2 O'her Sptems Interfaces (a) Synchro A or E position bypass (t)) Rod server module channel A or B bypass (1) Alternate Rod Insertion (ATWS) (Anticipated (c) Uncoupled condition bypass Transient Without Scram)
(d) File control module channel A or B bypass The RC&lS logic, during an anticipated tran-(c) ARBht channel A or b bypass sient without scram (on receipt of signals (f) htRBhi channel A or B bypass as a result of high reactor dome pressure or (g) RPC channel A or B bypass low reactor water level) initiates ARI sig.
(b) RACS channel A or B bypass cals which controls the fine motion control (i) DAhi channel A or B bypass rod drive motors such that all control rods are driven to their full in position automa.
(11) Scram Time Test Data Recording tically. The four divisions of the nuclear boiler system provide each of the two The logic of the RC&lS provides tne capabi- channels of the RC&lS logic with the reacter lity to automatically record individval fine high dome pressure and reactor low water motion control rod drive (FhtCRD) scram level signals for generation of the ARI timing data based upon scram timing reed signal based on two out of four logic.
switches. When a particular PhiCRD scram timing switch is activated, the time of The operator at the RC&lS dedicated display actuation is recorded by D Ahls for time can take action and initiate the ARI func-tagging of stored scram tir. $ cst data for tion. Two manual actions are required to that particular fine motion cont al rod manually initiate ARI. The RC&lS logic has drive. The time tagged data is stored in been designed to complete the ARI functions i memory until the next actuation of that in the worst case non accident environment, l particular reed switch is detected again, completely independent of reactor pressure
- transient conditions. This capability is The RC&lS also time tags the receipt of a accomplished with control logic for inser-reactor scram condition being a:tivated tion of all control rods by an alternate and based upon the scram following function diverse method, based on receiving reactor input signals from the reactor protection high dome pressure and low water level (Le-system which is received via the essential vel 2) signals for generating its own ATWS multiplexing systeru. (anticipated transient without scram) sig-nal. The logic of the RC&lS has been de-The resolution of this time tagging feature signed such that no single failure results is less than 10 milliseconds. Contact in failure to insert more than one operable bounce of the reed switch inputs and the DAh! control rod when the ARI function is inputs are properly masked to support this activated.
function. 'the reference real time clock for time tagging is the real time clock of the (2) Recirculation Flow Control Sptem RC&lS.
The recirculation flow control system (RFCS)
When RC&ls detects a reactor scram provides each of the two channels of the condition, the current position of all RC&lS with two separate isolated trip control rods in the core are recorded, time signals indicating the need for automatir ;,
l tagged, and stored in memory. RC&lS logic selected control rod tur .4 (SCRRI). The signals are treated as nonsafety related l$
i stores this data in mernory until a request I is aceived from the performance monitoring signals within the logic of the RC&lS.
and control system. The taansmitted data is used by the PhtCS to calculate and summarire The RFCS provides signals to both channels 1
Arnendment 3 7.1 17 i
- I N S G ST A (12) ATLM Algorithin Description The ATLM is a microprocessor based subsystem of RC&IS that executes tut dif ferent algoritluts for enforcing fuel operating therrnal limits. One algorithm enforces operating limit minimu:n critical power ratio (OMCPR), ani the other the operating limit minimum linear heat ge: . ration rate (OLMMcR),
For OMCPR algori.:hm, the cora is divided into 48 regions; each region consisting of 16 fuel bundles. For OLMMCR algorithin, each region is furthe vertically divided up into four segments. During a calculation cycle of ATL (about 100 milliseconds), rod block setpoints (RBS) are (.alculated for OLMCP monitoring (48 values) and for OMU1GR monitoring (48 x 4 values). Then the calculated setpoints are compared with the real time averaged LPRM readings for each region / segment. The ATM issues a trip signal if any regionally averaged LFRM reading exceeds the calculated RBS. This trip s'.gnal causes a rod block within RC&IS and also a flow change block in the Reirculation Flow Control System (RFCS).
Provided below is a summary description of OMCPR and OMMCR RBS calculation methodology.
(a) OMCPR PBS Calculation Methodology. The 16 fuel bundles of each region are surrounded by four LPRM strings. There are four LPRMs in each string. For regional OLMCPR monitoring, the sum of the average of each Ir. vel of B, C, and D of the four LPRM strings is used. The formula f 3r calculating the OMCPR RBS is:
LPRMg*A o* RMCPRt RBS g - -
(1)
OLMCPR where:
RBS o Operating limit rod block setpoint.
LPRMt
- Initial sum of average of four LPRMs of B, C, and D levels that surround each region.
Ao . Margin factor for operating limit rod block; a known function of rod pull distan<e.
RMCPR t : Regional initial MCPR, i.e., the minimum CPR of the 16 bundles in the region spanned by the four LPRM strings. Rnown input from predictor (process computer).
OLMCPR : Operating limit MCPR in the current cycle; a known function of power.
.l.
I N S G ft h A CQNTlHU6D Formula (1) is applicable to cases where there is no core flow enange end when only one control rod is moved. Adjustmentss are made to the calculated RBS o to account for changes in core flow and adjacent control rods movements.
(b) OLML4CR RBS Calculation Methndolony. The formula for calculating the OLMuiGR RBS is:
LPMi (X)
- B m *M p MAPRATi (X) where:
RSS,(X) : Calculated operating limit warimum average planar l linear heat generation rate (OLMAPUICR) RBS at LPRM level X.
LPMt (X): Initial avarage of the four LPRMs (level X) at the four corners of each 16 bundle fuel region. The region monitored by the X level LPRM is the region covered up to 1.5 feet above and below the LPM (3 feet total).
B(X) : Margin factor for MAPuiCR operating limit rod block for X level LPRMs. A knoen function of power and rod position.
Kp : Off rated power factor to consider overpower condition during worst transient at off-rated condition. A known function of power.
MAPRATi (X):
Regional initial maximum MAPRAT for level X, i.e., the maximum MAPRAT of the 16 bundles within the 3 feet section covt. red by the X level LPRMs. A kneen input from thu 3D monitor.
! In formulas (1) and (2) above, " initial" refers to values that are l
downloaded from the "3D Predictor Monitor" subsystem of the plant Performance Monitoring & Control System (PMCS). A download is requested by ATLM whenever changes in reactor power and/or cose flow exceed a preset limit. A download i can also be manuclly requested by the operator, l
1 2-