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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 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 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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Standard Plant CHAPTER 4 TABLE OF CONTENTS (Continued) l Section Illlt P.agt 4.4.2 Description of the Thernal and Hydraulie Design of the Reactor Coolant Sptem - 4.4 2 4.43 Intx: Lgo5e Por 4.4 4 m
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-4.5.1 Control Rods Sptem Structunt Materials 4.51 4.5.2 Reactor Internal Materials 4.53 - -
4.53 Interfaces 43-4a 4.6 Bd.CDD1%.DI, SIGN OF REACTIVTIY COVTRhi.5Y33IMS ;
4.6.1 Information for Control Rod Drive Sptem 4.6 1 4.6.2 Evaluations of.the CRDs 4.6-10' 4.63' Testing and Baluation of the CRDs 44 13 444 Information for Combined Performance of Reactivity Control Sptems 4.6-16
--4.6.5 Evaluation of Combined Performance 4.616 APPENDIX 4A TYPICAL COh"lROL ROD PATTERNS AND ASSOCIA*IID POMTR -
DISTRIB1 MON FOR ABWR 4A 2 APPENDIX g _ FUEL UCENSING ACCEPTANCE CRITERIA APPENDIX fC. CONTROL ROD LICENSING ACCF.PTANCE CRITERIA 4 111 Amendmem 5
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'l CONTENTS (Continued) 1 Section Mt East 4.4.2.1.2 Reactor Coolant Sprem Therma 1 Hydraulic 4.42 is Data 4.4.2.13 Reactor Coolant Sptem Geometric Data 4.4.2 4.4.2.2 Operating Restrictions on Pumps 4.4 2
- .4.4.23 Power Flow Operating Mar 4.43 Limits for Normal Operations 4,4-2
.4.4.2J 1 -
4.4.23.2 Other Performance Characteristics 4.62 4.4.23.3 ReSi ons of the Power Flow Map 4.4-3 4.4.23.4- Design Features for Power Flow Map 4.&3
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- [4A.3 Loose-PartsMonitoringSystem. -y ;
v7 . The applicant referencing the ABWR design ~
t-shall provide alloose parts monitoring system on'
- - the reactor pr' essure vessel, and implernent a' ,
2 loose parts detection program whleh conforms to i the guidelines of the regulatory-position -
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contained in Regulatorr Onide 1.133.' The designi (:;--- INSGM.k of the loose parts monitoring system is deferred -
f so that it may be' defined utill21ag commercially
- availible componer.ts, at the time of construe. -
l tion, integrated with other instrumentation.
-systems and it can reflect the applicants preference and experience. :Se'e Subsection Q4,4.3 for laterface requirements; Fw 74,43 gag,,q,,,,. cod U c.e.wra Mem oboA ,
L4.4.4.1 Fower Flow Operatink Map The specific power flow operating map to be
- used at the plant will be provided by the utility to the USNRC for information. )
{4.4.4.2 neraal Limits = '
L The thermal limits for the core loading at
, th'c ytant will be provided by the utility to the USNRC for Information. ,
4,4.4J Loose parts Moaltoring System
)- i 1The applicant referencing the-ABWR design- '
e, > twill provide a loose parts monitoring system and: *7
- implement a loose-parts. detection program'(See ik Subsection 4.4.3). {.
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. l t4 SGftT A The j'cose farts)fonitoring Jystem (LPMS) is designed to provide detection of ,
loose metallic parts within the reactor pressure vessel. Detection of loose parts can provide the time required to avoid or mitigate safety related damage to or malfunctions of primary system components. LPMS detect structure borne sound that can indicate the presence of loose parts impacting against the reactor pressure vessel internals. The system alarms when the signal amplitude exceeds preset limits. The LPMS detection system can evaluate some aspects of selected signals. However, the system by itself will not diagnose the presence and location of a loose part. Expert diagnostic by an experienced LPM engineer is required to confirm the presence of a loose part.
4.4.3.1 Power Generation Design Bases The LPMS is designed to provide detection and operator warning of loose parts in the reactor pressure vessel to avoid or mitigate safety-related damage to or malfunctions of primary system components. The LPMS is not classified as a safety-related system, although it is designed in conformance withgegulatory Guide _1.133.
Additional design censideratiens provide for the inclusion of electronic features to minimize operator interfacing requirements during normal oparation and to enhance the analysis function when operator action is required to investigate potential loose parts.
4.4.3.2 System Description The LPMS continuously monitors the reactor pressure vessel and apourtenances for indications of loose parts. The LPMS consists of sensors, ca)1es, signal conditioning equipment, alarming monitor, signal analysis and data acquisition equipment, and calibration equipment. The alarm setting for
.each sensor is determined after system installation is complete. The alarm setting is set low enough to meet the sensitivity requirements, yet is designed to discriminate between normal background noises and the loose part impact signal to minimize spurious alarms. Each sensor channel is isolated
- to reduce the possibility of signal ground loop problems and to minimize the background noise. Background noises are also minimized by use of tuned filters. ' A disable signal is provided during control rod movement and other plant maneuvers that may initiate a spurious alert-level alarm.
LPMS sensors aro usually accelerometers. The array of LPMS accelerometers typically consist of twelve to twenty sensors that are strategically mounted on the external surface of the primary pressure boundary at various r
elevations and azimuths at natural collection regions for potential loose parts. General mounting locations are at the a) main steam outlet nozzle, b) feedwater inlet nozzle, c) core spray nozzles, and d) control rod drive housings. Tne sensors will be mounted in such a fashion as to provide high l
frequency response and sensitivity.
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. JThe online system sensitivity is such that the system can detect a metallic
- 1oo'se part that weighs between 0.25 lb to 30 lbs and impacts with a. kinetic-tenergy_of 0.5 ft-lb on.the.inside surface of the reactor pressure vessel within 3 feet of.a-sensor.- The LPMS frequency range of interest is
-typically from 1 to-10 kHz. Frequencies lower than ~1 kHz are generally associated with flow induced vibration signals or flow noise, Physical separation is maintained from the sensors at each natural collection region to an area where-they are combined and routed through the cable penetration to a termination point. The termination point is at a point'in the plart.that is accessible for maintenance _during full power operation.
The LPMS includes ~ provisions for both automatic and manual start-up of data acquisition equipment with automatic activation in the event the preset
. alert level is reached or exceeded. The system also initiates an alarm to
- the control room personnel-when an alert condition is reached. The data acquisition system will automatically select the alarmed channel plus additional channels for simultaneous recording. The signal analysis-equipment willf allow-immediate visual and audio monitoring of all signals.
Provisions exist for-periodic online channel check and functional tests and for offline channel calibration during periods of cold shutdown or .
refueling.:- The LPMS electronics is designed to facilitate the recognition, location, replacement, repair, and adjustment of malfunctioning-LPMS components.. The <lPMS components-located inside the containment have baen i designed-and--installed perform their function following all_ seismic events that do not_ require plant shutdown, up to and including the Operating Basis Earthquake..'The LPMS components selected for this application are rated to meet the normal c aerating radiati.on, vibration, temperature, and humidity environments in witch the components are installed.
go Go.
A11~LPMS_ component: within the corta ment are designed for a pfyear design
-life. In those instances where-a year design life is not practicable, a replacement program'will be established for those parts that are anticipated
- to have limited-. service life.
.4.4.3.3 Normal System Operation
. The LPM 1will be set to alarm for detected signals having characteristics of metal-to-metal impacts.
After; installation # the sensor array, the LPMS overall and individual channels can be characterized at plant start-up before' operation monitoring.
- Each accelerometer channel will exhibit its own particular and unique frcquency spectrum.< This frequency signature, or normal background noise, L results from-a combination of both internal and external sources due to j snormal and transient conditions.
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- : \ td SWLT A ( Co uD Y-Calibration'is an important-part of LPMS operattun. The LPMS is calibrated to detect a loose part with minimum impact energy of 0.5 ft-lb within 3 feet of a sensor. Alarm level setpoint is determined by using a manual calibration device to simulate the presence of a loose part impact near each sensor. The setroint it, typically a based on a percentage of the calibration signal magnitude, and is a function of actual background noise.
Additionally, calibrated impacts at various locations near the sensors assist in diagnosing the source of the signal.
Discrimination logic is typically incorporated in the LPMS to avoid spurious alarms. Discrimination logic rejects events that do not have the characteristics of an im>act signal of a loose part. Typical discrimination functions are based on t1e length of time the signal is above the setpoint, the number of channels alarming, the time between alarms, the repetition of the signal, and the waveform and frequency content. False alert signals due to plant maneuvers are avoided by the use of administrative procedures by control room personnel.
Once an unusual signal characteristic of a metal-to-metal impact is detected by the loose parts monitcr, it is essential to determine the source or cause of the alarm. An alarm does not necessarily indicate the presence of a loose part in-the reactor. The alarm could be caused by electrical noises, system malfunctions, limitations in alarm logic, or non-impact noises. The LPMS detection system is designed to incorporate the discrimination logic to distinguish between an actual loose parts signal and a non-loose parts signal before signaling the control room operator.
Usually the plant. operator makes the preliminary evaluation based on the available information. If the presence of unusual metal impact sound is ii.dicated, then the station engineers perform additional evaluation. LPH experts are required to correctly diagnose the p*esence and location of a loose part. In order to reach proper conclusions, various factors must be considered such as: plant operating conditions; location of the channels
-that alarmed; time differences between when the wave arrived at different locations; 2nd comparison of the amplitude and frequency contents of the signals with known normal operation data.
4.4.3.4 Safety Evaluation The LPMS is intended to be 'used for information purposes only by the plant o)erator. The plant operators do not rely on the information provided by tie LPMS for the performance of any safety-related action. Although the LPMS is not classified' as a' safety-related system, it is designed to meet the seismic and environmental operability recommendations of Regulatory Guide 1.133.
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'i (N 3gg;p A ( C O N T) 4.4.3.5 Test and Inspection The LPMS will be calibrated to detect a metallic loose part that weighs from 0.25 lb to 30 lbs and impacts with a kinetic energy of 0.5 ft-lb within 3 feet of each sensor. Provision will be made to verify the calibration of the LPMS'at each refueling. The system will be recalibrated as necessary when found to be out of calibration. A test and reset capability will be included for_ functional test capability.
The manufacturer will provide services of qualified personnel to provide technical guidance for installation, start-up, and acceptance testing of the-system._ In' addition, the manufacturer will provide the necessary training of plant personnel for proper system operation and maintenance and planned operating.and record-keeping procedures.
4.4.3.6 Instrumentation Application The LPMS consists of sensors, cables, signal conditioning equipment, alarming monitor, signal analysis and data acquisition equipments and calibration equipment.
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