|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld ML20195G4591999-06-10010 June 1999 Forwards MORs for May 1999 & Revised Repts for Apr 1999 for LGS Units 1 & 2 ML20195H0531999-06-0909 June 1999 Forwards Revised Bases Pages B3/4 10-2 & B3/4 2-4 for LGS Units 1 & 2,in Order to Clarify That Requirements for Reactor Enclosure Secondary Containment Apply to Extended Area Encompassing Both Reactor Enclosure & Refueling Area ML20195E7701999-06-0707 June 1999 Provides Notification of Change to NPDES Permit PA0052221, for Bradshaw Reservoir Facility Which Supports Operation of Lgs,Units 1 & 2,per EPP Section 3.2 ML20195C7631999-06-0101 June 1999 Notifies NRC That PECO Energy Has Completed Installation of New Large Capacity,Passive Strainers on RHR & Core Spray Sys Pump Suction Lines at Lgs,Unit 2,in Response to Ieb 96-003 ML20195D5381999-05-26026 May 1999 Forwards 1998 Occupational Exposure Tabulation Rept for LGS Units 1 & 2. Encl Is Diskette & Instructions.Rept Is Being re-submitted to Reset 12 Month Time Period.Without Disk ML20195B2821999-05-24024 May 1999 Requests That NRC Distribution Lists for LGS Be Updated. Marked-up Distribution List Showing Changes Is Attached ML20196L2891999-05-20020 May 1999 Provides Status Update of Thermo-Lag 330-1 Fire Barrier Corrective Actions,Iaw Commitments Made in ML20195B2951999-05-20020 May 1999 Forwards Rev 0 to LGS Unit 2 Reload 5,Cycle 6 COLR, IAW TS Section 6.9.1.12.Values Listed Have Been Determined Using NRC-approved Methodology & Are Established Such That All Applicable Limits of Plants Safety Analysis Are Met 05000352/LER-1999-003, Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv1999-05-19019 May 1999 Forwards LER 99-003-00,re Rps,Pcrvics Actuations.Ler Contains Special Rept Info for HPCI & Reactor Core Isolation Cooling Sys Injections Into Rv 05000353/LER-1999-002, Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 9904191999-05-18018 May 1999 Forwards LER 99-002-00,automatic Actuations of Primary Containment & Reactor Vessel Isolation Control Sys & Other Common Plant ESF Due to Loss of Power to a Rps/Ups Power Distribution Panel on 990419 ML20206E2001999-04-28028 April 1999 Forwards 1998 Annual Environ Operating Rept (Non- Radiological) for Limerick Generating Station,Units 1 & 2. Rept Submitted IAW Section 5.4.1 of App B of Fols,Epp (Non- Radiological) & Describes Implementation of EPP for 1998 ML20206D8801999-04-27027 April 1999 Forwards Rev 2 to LGS Unit 1 Reload 7,Cycle 8 COLR, IAW TS Section 6.9.1.12.COLR Provides cycle-specific Parameter Limits for Noted Info ML20206A5461999-04-21021 April 1999 Responds to Conference Call Between Util & NRC on 990420,re TS Change Request 98-07-2,revising TS Section 2.0 to Incorporate Revised MCPR Safety Limits.Attached Ltr Contains Info Requested ML20205T0441999-04-17017 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept 15, IAW TS Section 6.9.1.7.REMP for 1998,confirmed That LGS Environ Effects from Radioactive Release Were Well Below LGS TSs & Other Applicable Regulatory Limits ML20205Q7581999-04-15015 April 1999 Forwards Response to RAI Re ISI Program First & Second 10-Yr Interval Relief Requests.Revs to Identified by Vertical Bar in Right Margin 1999-09-09
[Table view] Category:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20058L8901990-07-30030 July 1990 Advises That FEMA Grants Exemption from 10CFR50 App E for Biennial full-participation Onsite/Offsite Exercise ML20248E1141989-07-31031 July 1989 Forwards Radiological Emergency Preparedness Exercise Evaluation Rept,Limerick Generating Station, for Exercise on 890614.Deficiency Noted Re Inadequate Response Capability by Lower Pottsgrove Township ML20247K4031989-05-19019 May 1989 Forwards Final Exercise Rept for 890405 Exercise of Offsite Radiological Emergency Preparedness Plans site-specific to Facility.One Deficiency Noted Re Lower Pottsgrove Township Emergency Operations Ctr ML20247N1291989-05-19019 May 1989 Forwards Final Exercise Rept for 880405 Exercise of Offsite Radiological Emergency Preparedness Plans site-specific to Plant.Offsite Preparedness at Plant Not Adequate to Provide Reasonable Assurance That Public Health & Safety W/O Risk ML20236L2461987-07-30030 July 1987 Discusses Participation of Certain Ingestion Exposure Pathway EPZ-only States in Qualifying Exercises Used by NRC in Making Licensing Decisions for Operating Exercises.Listed Plants Noncompliant as of 870331 ML20212P3671987-03-0303 March 1987 Forwards Limerick Generating Station Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification. Alert Sys Satisfies Requirements of Rev 1 to NUREG-0654/FEMA-REP-1 & FEMA-43 ML20214M6591986-09-0202 September 1986 Responds to NRC 860729 Request Re Establishment of Addl Traffic Controls on Pennsylvania Turnpike at Route 100. Chester County Radiological Response Plan Includes Placement of Three State Police Officers on Turnpike ML20204F2011986-07-29029 July 1986 Forwards Exercise Evaluation Rept for Limerick Generating Station for 860403 Exercise of Offsite Radiological Emergency Preparedness Plans.No Deficiencies Noted.Areas Requiring Corrective Actions Listed ML20135C1771985-09-0606 September 1985 Notifies of Util Application for Permit Re Use of Cooling Water from Beechwood Pit Filed W/Delaware River Basin Commission.Questions Raised Re Effects of Water on Quality of Schuylkill River & Need for Addl EIS-related Work ML20133G6411985-08-0606 August 1985 Supports Pennsylvania Emergency Mgt Agency Request to Exempt Chester County from Full Participation in Joint Exercises Involving Peach Bottom,Providing County Participates in Limerick Exercise ML20126J3191985-06-0606 June 1985 Forwards List of Local or Regional Medical Facilities Having Capabilities to Provide Treatment for Radiation Exposure in Vicinity of Plant,Per 850528 Request ML20129C0201985-05-30030 May 1985 Updates 850521 Memo Re Plant Offsite Planning & Preparedness.Verification That Traffic Control & Access Control Points Will Be Established in King of Prussia Area to Keep Evacuating Traffic in Motion Received ML20128C7241985-05-21021 May 1985 Forwards 850418 & 25 Draft FEMA Region III Exercise Evaluation Rept, of 850410 & 22 Remedial Exercises, Respectively ML20100J6951985-04-0909 April 1985 Forwards Pp Giordano 850329 Memo Forwarding Supplemental Findings on Offsite Radiological Emergency Preparedness for Facility.Deficiencies Listed.Plan Deemed Inadequate ML20127D6561985-03-27027 March 1985 Discusses 850307 Remedial Exercise at Graterford State Correctional Institution in Support of Facility.Portion of Category a Deficiencies Cited on 840725 Corrected ML20106E2981985-02-0101 February 1985 Forwards Exhibit Status Rept Re FEMA Exhibits Addressed at Hearing in Facility Proceeding ML20104A7061985-01-23023 January 1985 Responds to 841226 Memo Re FEMA Support for NRC Licensing of Facilities.Clarification from PA Emergency Mgt Agency Re Nature & Scheduling of Review of Revised Plans Requested. Index to Revised Plans Requested by 850201 ML20112H1971985-01-10010 January 1985 Forwards Exercise Evaluation Rept for 841120 Supplemental Exercise of Offsite Radiological Emergency Preparedness Plans.Supplemental Exercise Conducted to Correct Deficiency Identified in Initial Full Participation Exercise on 840725 ML20108E1221984-12-11011 December 1984 Forwards 841126 Notice of Appearance Re Offsite Emergency Planning Hearing,In Response to Request ML20094A9021984-11-0202 November 1984 Forwards FEMA Prefiled Testimony on Offsite Planning Issues. W/O Encl.Related Correspondence ML20098E3921984-09-25025 September 1984 Forwards Evaluation of 840725 Exercise of Offsite Radiological Emergency Preparedness Plans for Limerick.Plans Inadequate.Schedule of Corrective Actions Under Review ML20096E6741984-09-0505 September 1984 Discusses FEMA Position on ASLB Request for Release of FEMA Regional Draft Rept Re Jul 1984 Exercise to ASLB & Parties Prior to Review at Headquarters.Fema Has Never Released Unreviewed Repts of Subj Type ML20091P6631984-06-0606 June 1984 Comments on Fes Re Surface Water Hydrology & Water Quality. Comments Support Recommendation for Evaluation of Impacts During Schuylkill River Extreme Low Flow Conditions ML20091G3451984-05-25025 May 1984 Forwards FEMA Regional Assistance Committee 840427 Informal Evaluation of Offsite Radiological Emergency Response Plan. Rept Is Addendum to 840508 Interim Findings ML20084J8231984-05-0808 May 1984 Forwards Interim Finding on Offsite Radiological Emergency Response Plans for Limerick Generating Station,Apr 1984 ML20083P6051984-04-17017 April 1984 Informs of Error in Fourth Line of Second Paragraph of First Technical Comment, Statistics & Probability. Sense of Paragraph Stated as Either/Or Situation Recommended ML20080S7861984-02-27027 February 1984 Forwards Original Typescript of Revised Comments Dtd Feb 1984 to Be Appended Into Fes.Corrected Version Supersedes Jan 1984 Version ML20087E1011984-02-10010 February 1984 Notifies That Natl Ctr for Devices & Radiological Health Has No Comment Re Postulated Plant Accidents Described in Des (NUREG-0974) ML20080P2851984-02-0808 February 1984 Comments on Suppl 1 to Des for Facilities.Consequences of Severe Accidents on Schuykill River Not Clarified & Adverse Effects on Fish & Wildlife Not Considered ML20080B9751984-02-0303 February 1984 Forwards Technical Comments Based on Review of Suppl 1 to Des.Nrc Should Consider Risks Associated W/Range of Events Expected to Occur Offsite.Documents Rated as ER-2 ML20079Q3841984-01-27027 January 1984 Offers No Comments on Des ML20080A4761984-01-21021 January 1984 Forwards Responses to Doi 830826 water-related Comments on Des.Clarification on Listed Water Resource Issues Requested ML20083J2481984-01-0909 January 1984 Advises That Suppl 1 to Des Reviewed.No Substantive Comments Made ML20076G4571983-08-29029 August 1983 Forwards Comments on Des.Advance Notification of Planned Activities Disturbing Geodetic Control Survey Monument Requested ML20076G2911983-08-26026 August 1983 Comments on Des Re Water Reservoirs Water Quality & Environ Impact.Paragraph in Section 43.1.1.3 Should Be Revised to Reflect Severity of Low Flow Problems in Delaware River ML20077J6861983-08-15015 August 1983 Forwards Comments on Des for Plants.Document Acceptable & Rated ER-2 Meaning Environ Reservations Are Related to Insufficient Info.Comments Concerned Primarily W/Radiation & Cooling Water ML20077H5461983-08-0505 August 1983 Advises That Review of Des for Facilities Completed.No Comments Offered ML20077G1921983-07-29029 July 1983 Comments on Des (NUREG-0974) Dtd June 1983.Calculated Doses to Individuals & Populations Resulting from Effluent Releases Are within Radiation Protection Stds ML20077D3911983-07-22022 July 1983 Advises of Incorrect Interpretation in Des of Delaware River Basin Commission Water Quality Stds Re Mixing Zone for Discharge of Constituents Such as Residual Chlorine ML20076M3751983-07-15015 July 1983 Concurs W/Nrc Conclusions Re Des for Facility,Per NRC 830624 Request.No Detectable Effects to Delaware River from Facility Operation Expected ML20073L7501983-04-15015 April 1983 Comments on Evaluation of Soil & Rock Slopes at Plant Site, Per Interagency Agreement.No Offsite Slopes Identified Which Would Affect Safety of Seismic Category 1 Sys ML20079H4081982-12-0707 December 1982 Forwards Pages from Design of Water Intake Structures for Fish Protection, Re Velocity Difference Across Intake & Potential for Biofouling Even in Fresh Water ML20062K5771982-08-10010 August 1982 Forwards Motion on Behalf of Gm Hansler Re Application Filed by Del-Aware for 820817 Deposition.Absence of Gm Hansler Requires That Motion Be Denied or Deposition Be Rescheduled for 820830 ML20058E9421982-07-27027 July 1982 Advises of Intent to Participate in Des Review,In Response to 820614 Request.Related Departmental & Svc Correspondence Encl ML20054L3671982-06-30030 June 1982 Informs That No Threatened or Endangered Species Exist in Area of Site,Except for Occasional Transient Species.Natl Marine Fisheries Svc Should Be Contacted to Determine Need for Biological Assessment ML19347E8771981-04-21021 April 1981 Forwards Public Notices for Proposed Const of Water Diversion Structures Near Point Pleasant,Bucks County,Pa by Neshiminy Water Resources Authority ML19351G3831981-02-17017 February 1981 Advises of Desire to Participate in Project Scoping Meetings to Address Past Concerns & Provide Timely Resolution During EIS Preparation ML19338C4071980-08-11011 August 1980 Informs That Jf Devine 800725 Ltr Re Distances from Future Blasting & Class 1 Structures Should Have Substituted Word Max for Min ML19330B4871980-07-25025 July 1980 Forwards Response to NRC 790809,0918 & 1018 Ltrs Requesting Review of Matl Relevant to Determining Facility Response to Nearby Quarry Blasting.Blasting Will Not Cause Damage to Any Class 1 Structures ML19344F4811980-07-25025 July 1980 Forwards Borough of Phoenixville,Pa 800718 Ltr to President Carter,Transmitting Resolution 80-10 Opposing Const of Nuclear Reactors.Requests Response 1990-07-30
[Table view] |
Text
l l
'. .. , UNITED STATES s
- DEPARTMENT OF THE INTERIOR "-
I FISH AND WILDLIFE SERVICE
~
Suite 322 . l
% ,Y 315 South Allen Street @ 13 to .; ~
State College, PA 16801 A i.
CE:.L December 7, 1982 Mr. Lawrence Brenner Administrative Judge Atomic Safety & Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Judge Brenner:
I am enclosing several pages from a recent publication " Design of Water Intake Structures for Fish Protection". I have marked the sections referring to the 2:1 velocity difference across the intake and the potential for bio-fouling even in fresh water.
This is in support of testimony I gave November 22, 1982, on behalf of Del-Aware Unlimited, Inc., Philadelphia Electric Company (Limerick Generating Station Units 1 and 2), Docket No. 50-352-OL and 50-353-OL.
Even if this cannot be submitted as evidence in the hearings, I felt it may help you better understand the intake issue.
Sincerely, Richard W. McCoy Fish & Wildlife Biologist I
Enclosures 1
[
l i
1 l
9212160316 821214 PDR ADOCK 05000352 G PDR DEC 131092
' Design Of ,
t
' Water \
' Intake !
Structures
. 'For' Fish ' Protection -
. Prepared by the
' Task Committee on Fish-Ilandling Capability of Intake Stnictures I of the Committee on flydraulle Structures of the ifydraulics Division of the American Society of Civil Engineers t
L ll it
- i a
iI '
C4{. s thf%
l Published by the I
Arnetican Society.of Caval Engineers
i 129 5CR f f- NIMi I OR ORG % Int 5 1:* W All P INi ul NIHl1 Il His i
- 6. ine vra ivrari Jacking lerqth of the radial screeris ns in the order of 1
Li s a , g ' , ..t tr. . ; i t .s l .: 11 int 4ke s , , t ,-ti J
- I Ir" ' J 31 3 5 e e- l l is 4nly w i t s b l e n r ..-r e t'.ef e is a porGus arjite, . i t y, tt and 300 f t ( 45. 7 and 31.4 m) . O ta neter does net at er ec iatil y
. n. n i t , tu i r. , t le tr,e qu 3n t i t ,' ut ster rewirel. un t ce tanstely, t ,4 '"' "'" "9 '" # ,
i r. t 2 6 e si'-s ttst c an r < saitault de eld eJ are l i r. i t e d . Vertitst 7. Inflow velocity throu4h screen pertorations ranqes from I to 2 fpm j t e.s t -e'Is ..t te drille1 snJ testej to seterm me the cnaracteris-(0.30 to 0.tl m/ min). The to.er velocities are suttatsle f or fine
,tt of toe a a t 'er tod tr e o mi tude of the re+4 t r ed collector sys.
sand aquif ers or corrosive waters.
tew. un s test in ; pr+;r sm ma y toe trum twa to four n.nths. 8. Net open area of the perforated screen ranges from 18 to 22 percent
/ 7,+ in11v' L s1 tsissJn units ar e lin ite t to ob.aut 25.000 ;sl /nin with the Idrger percentage generally applying to larger screens.
i c I <a ._,1/ain) tyt p c.b s t. l y mut. h les> in r, cst usatle alutfers. fo Regatred beam strength is a criteria. Perforattert sizes range from
,e t j e j s r . , .- r .oter r ew t rw ent s , wide l , spited n.ul t iple uni t s are '. .083 to 0.375 in. (2.0 to 9.5 mm) wide depending on the geolo-i te nie e t ud ill mu.t t,e ornette1 to a wrw transansstcin pipe alcal characteristics of the aquifer.
Assuming typicel values of Id percent open area and an inflow velo-to t rir i I v.t 3.
city of I f an (0. 30 m/ min), the total length of laterals can t.e vr. ur n a t i a tor n .lic,ina,j ne , i p ' #
i i s t ed t.e l ow ir e t ypitil charatteristics tur a rsdist well inta6e. This int eit ii n will t e nt , a l .,e in de t er minirq t he nroer ut ma3nttude of such an 1W ? 98I #*b" --
I L (f t) = $creen Diameter Unches) inti6" for s it en inte i
3 I
I Ite aw al s; e ity of todiviLsl (cliettcr- anits is in the 1,000 --- b- -"I
to l'1,uu0 ,21 Nin (4 to 40 m / min) ranye, tnat c aul d 90 as high L (m) = Screen Diameter (meters)--
a s hot J5,ma pl / nin ( 100 m /lmin) ' in a very f avoratale aquifer.
"ir r i 21t J I = ells h s ,e t.een plu ed in relatively th1n aq91ters with 10. Low Cart,on steel is the usual Collector screen material. In relatively noncorrostve waters, a minimum lite of 30 years can t;e e=pected. In it~tte!.sucity'
( a i ssun sp+ In j for multtple units is typically 1,500 ft corrosive waters and where longer life is desired, statnless steel or t u l l ei t o r
( N a. ) . An array of tullettors may thus spr ead over a large dres. Other corrosion resistant material can be used.
The liswter of the caisson depen'1s un the space reqairements f or 1
Subsurface borings must be made to develop site specific design information t t.e p.a p s a n 1 <.n the tiesrsm e needed for lateral screen Jacking for afiy but a very preliminary design. If the borings indicate one or more g eritioni ',a.a l l es t r ea 2 t l y availat21e f orms are f or a 13 f t (3.96 m) ,
potential aquifers, then vertical test wells for test pumping and for ground in.ide Ini eter toni r et e taisson. A f 6 f t (4.M m) 10 is a water level observations must be drilled and a test program undertaben in the typtial site same general manner required for proving out a vertical well installatiori,
- 4. i.aissoris plat e1 to depths uf up to J00 f t (61 n.) f rom the surf ace are fer.ible. Wter may tie dra.n trom two or more separate MMM 9h0PMi% PW IMM a piter s it r ei.nsar y , wi th ra li s i st reens jat6ed into the aquifers
'""'I ",The presentiv recorimended small-opening pipe intake for the reduction at different elevations from inside the (ais un. f entrainment is similar to the cylindrical pipe concept discussed in Chapter S. The t yp h a t t i twier of radial collettur screens is 8 to i6 in, * ' ' "9 " '" ' " "" $'
I N 3 16 40.h tit) but slles to 4d in. (122 tm) tould t>e con-j '.1 dW e"1 f i.e J2iling loto a very hi.[h yield aquifer.
a, h
4
I SCREENING l'OR ORGANISMS 138 130 W ATER INT AKE STRtJCTt!RES .
- 1. The openings are much smaller, say 0.02 to 0.08 in. (0.5 to 2 m) wide, However, it could tm expected that some of the early larvae of many species would coer,areJ with 1/4 in.
3/8 tr.. . or 1/2 in. (6.4 m. 9.5 m. or 12.7 mm) ;
be susceptible to entrainment. Further with 0.04 in. (1.0 m) slot openings, g normally used for cylindrical pipe intakes. ! eggs or some species would also be subject to entrainment.
Field studies (11) have been conducted with profile-wire screens to deter-
- 2. Due to the very small openings, periodic clogging by impin9ed material Mne Nk pdential & Mn ng emainment at a pmpoW mer Mant to M or biological growth must be expected and the screen system. therefore j located on the St. Johns River in Florida, intake screens incorporating both ;
must be designed so that operators have easy access to the screen i O.04 to 0.08 in. (1 and 2 m) mes% were tested in situ via a simulated intake unit for cleanin9 Unlike the large-opening perforated pipe inlet.
structure; an unscreened intake pipe was utilized as a control condition. The it cannot be placed in deep water or far from shore where access ,
would t , dif ficult. results of these studies indicated that entrainment of fish larvae was reduced by the profile-wire screens by more than 60 percent as compared to the unscreened 4;though t.d openings in the pipe can be punched perforations (holes or intake pipe. Only small differences in entrainment were noted between the 0.04 s ts or profile wire. the profile wire is the favored screening eedium and and 0.08 in. (1 and Z e ) mesh screens.
its use will t,e assumed in the discussion. Unlike most of the intake screen The only field study of profile-wire screens for possible application to esigns reconsnended in this test. the concept af the small-opening profile- a once through cooling water system were conducted at the J. H. Campbell Plant w re scr*en is new and relatively untested. There are no installations for on Lake Michigan (12). The study design was sistlar to that described above power plant service presently in entstence. Many field tests are presently except that mesh sizes of 0.08 and 0.37 in. (2 and 9.5 m) were tested in com-underway and have clearly indicateJ at least some measure of entrainment pa-ison to an open intake pipe. In this case. It was also concluded, based on y reduction. The comittee accordingly recommends consideration of small-opening plankton net tow data, that a profile-wire screen intake would reduce entrain-profile wire screen in light of t.ie scarcity of alternative means for reducin9 ment. However, no significant differences in entrainment were detected be-antrainment, tween either mesh size or the open pipe. Therefore. the mechanism by which
)
the apparent reduction in entrainment into the screens and pipe occurred is Biological Considerations - Stological research on cylindrical. profile-wire unclear. Nevertheless a profile-wire screen intake has been installed and screens indicates that they could be relatively effective in preventing the en-is operating at the Campbell Plant. supplying water on a once-through basis }
trafnment of fish eggs and most larvae at power plants provided that the screen slot size is small (appron%4tely 0.02 to 0.04 in. (0.5 to I.0 m). that the
% a suwged kcation mer M f t W8 4 Whe. m t N h M in, (9.5 m). not the small size being considered in this section. Operational data ,
through-slot velocity is low approximately 0.5 fps (0.15 m/sec) and that a relatively hi9h velocity (1.0 fps (0.30 m/sec) or greater) cross-flow exists are not available at this writing.
Due to the small slot size. 0.02 to 0.04 in. (0.5 to 1.0 m), and slot velo- ,
to carry organisms around and away from the screen (9).
city. 0.5 fps (0.15 m/sec), entrapment or impingement of juvenile and adult In laboratory studies. Hanson et al. (10) found that entrainment of fish fishes would not be expected to occur. Therefore, the profile-wire screen e995 (striped bass) ranging in diameter from 0.07 to 0.13 in. (1.8 to 3.2 mm) alternative appears to offer a potentially effective means of reducing fish could t,e eliminated with a profile-wire screen incorporating 0.02 in. (0.5 m) slot openings. However. striped bass larvae. 4 to 20 days old, measuring Iosses.
0.2 to 0.37 in. (5.2 to 9.2 mm) were generally entrained through a 0.04 in (1 m) slot at a level exceeding 75 percent within 1 minute of release in the tist fiume. Larval tests were conducted in a static mode with no crossflow passing the screen. It was concluded that, since positive rheotants was observed tmong these early larvae. a crossflow would act to reduce entrainment to some ex- ,
tint. An ambient current could therefore help in preventing larval entrainment.
e ,
I 1
{
i 4
c>
{ ;
132 WAT ER INTAKE ST Rt;Cil1RES SCREENING FOR ORGANISMS 333
- 1. Multiple screen untts are used. '
DECK FOR MANUAL
- 2. The screen units are small enoulh in size and weight to permit con-SCREEN CLE ANING l venient handling, j -
l . -A
- 3. The units are mounted in such a manner that they can be periodically l MULTIPLE REMOVABLE g "-g -j removed f rom the water and manually cleaned, inside and outside. It SCREEN UNITS is espected that normal operation will require a regular schedule AS REQ'D t_ ;g g O 3 of remoeal to clean off biological growth that cannot be removed by b ac 6 wa s h hg.
i Q
( 4 Piping downstream of the screens is designed so that individual j ,
l screen units can be isolated, backwashed, or removed without affect- l j ~
ing the operation of remaining units.
The following general factors must t,e considered when designing this type PLAN of screen:
Potential for clogging, especially from biological growth. Tests to date indicate significant, but manageable, biological growth in salt HOIST 8 MONORAll q water and a lesser growth in fresh water. The performance of the TO MANUAL z AIR COMPRESSOR screan is tnus site related. There is a significant difference in CLEANING AREA 8 ACCUMULATOR 53 the degree of biological fouling on various materldls available for fabricating the screens. Stainless steel is the standard WATER BACKWASH ~L_
material used for profile wire '.reens. Some alternative materials (OPTIONAL) t PUMP
o.
that are more effective in discouraging biological growth and can -
AIR BACKWASH .
be successfully fabricated using standard manufacturing procedures include 10-30 copper nickel, 90-10 copper nickel, Carpenter 20 (20%
{ f~*
b-{
=_
} , ,
thromium stainless steel), Ampco 8 (Aluminum bronze) and monel (13)(14). ~ b }* -
l ,
E 0 N Periodic painting with antifouling paints has also reduced biologi. ! SCREEN UNIT - ., 11 $4gE O cal growth in test installations. '
IN WALL GUIDES ' - -
% VALVE
- 2. Site of the opening required to achieve the desired results at a NN'*^N ' WJa * *
-x - : . a qiven site. Consider the size of the organism to be prevented from j
entering and use the largest opening that will produce the desired ,
I result.
Velocity of inflow. An average slot velocity of Inflow of abnut
O.5 fps (0.15 m/sec) has been a common figure used to date, riowever, Figure V.4 CYLINDRICAL SCREEN INTAKE WITH PULTIPLE MANUALLY CLEANABtE UNITS greater or less velocities may be better suited to a particular situation.
50 rco WM % 0) '
f 4
6 4
]
i .
t IM W ATER IN TAKE STRtiCTIJRES SCREENING FOR ORGANISMS 135 t
- 4. Geometry of the screen to give optimum performance. The sievle I small-opening Cylindrical screen will have the same poor velocity distribution characteristics as a simil#r larger opening screen ;
dtscussed in SECTION IV. The length should not exceed the diameter. '
and an internal projecting pipe or other internal velocity distri- l MPRESSED butor should be used.
j , VALVE REQ'D
- 5. Possible adverse influence of ice formation or ice collection on FOR BACKWASH l
the screen surface- WATER l]
, 6. Influence of adjacent screen units on one another, during both ' .
AIR {
normal flow and backwashing. Performance will be influenced by the direction and velocity of ambient currents at the point of water intake.
- 7. tiethod of t'ackwashing. As stated in SECT! ora IV for larger opening "A" BACKWASH BY AIR OVER WATER perforated pipe screens. air blast bac6 wash has been found to be effective. Air can be introduced into the lead-in pipe upstream COMPRESSED of the screen unit. Fig. V-5A or can be discharged from a multi- VALVE REQ'D ONLY ported header inside the screen unit itself. Fig. V-58. Testing FOR UNIT ISOL ATION has shown that the latter schem is more complex but more effective.
l l l If the air enters the lead-in pipe, then the screen unit must be AIR ;, s'fa ggg09, , ie e, e isolated by valve during backwashing. This is not necessary for l g the multioorted air header. Fig. V-58. An air blast volume of 2 to -
3 times the screen unit volume. at a pressure of 100 pst AIR HEADER (690 kPa). has been found to be ef fective in installed units se si 4tudied to date. It is desirable to remove all water from the air backwash piping upstream of the screen unit just prior (9 injection of the compressed air. This can be done by first bleeding air into the piping to displace the water.
Figure V-5 TYPICAL AIR BACKWASHING METH005 Adwyntajes of th,e small-Opening Cylj_ndr,ical, Pipe _ Intake.
I. The small screen openirg can be designed to keep many entrained Source: Richards (Ref. 41) organisms from entering the water system.
- 2. There is no conftned channel leading to the screens, thus eliminating ,
a possible area for entrapment of swimming organisms. .
2 i
y -
Q 136 WATER INTAKE S TRUCTURES g SCREENING FOR ORGANISMS 137 ,
- 3. The approach velocity to the screen face falls off very rapidly and Recommendations for Preliminary Design of a Small-0penin g ylindrical Pipe Intake is negligible a few inches from the screen, as discussed in SECTION tv for perforated pipe intakes and indicated in Fig. IV-32. The For preliminary design purposes the following parameters may be used in addition to those general factors enumerated above; tendency for swissung organisms to impinge is thus low. ,
4.
- 4. Impinged organisms can be removed by backwash without these organisms Screen unit diameters for the removable type of screen being discussed leaving the water, unme the traveling screen which is cleaned here have to date been in the range of 24 to 48 in. (61.0 to 121.9 cm). Coisnercial automatic winding of profile wire screen is above the water surf ace.
presently limited to 36 in. (91.4 cm) above which manual fabrica.
- 5. Trash bars, trash rakes. and traveling screens are not required. This tion is required. However, the overall cost of the screen unit vs.
is an advantage from economic, operational and maintenance points of flow capacity is not greatly increased by the manual fabrication, view. The manual cleaning of the cylindrical screen units requires Handling weight for convenient removal and washdown will be a factor less skilled personnel than the maintenance of traveling screens, in size selection.
Disadvantages of the small-Open_tng_ Cylindrical Pipe intake. b. Limit the length of the screen unit to the diameter of the screen
- 1. The site conditions must be such that relatively deep water is close or less and extend the outflow pipe into the interior of the to shore so that a structure similar to Fig. V-4 can be used. Unlike screen about 40 percent of the screen length. This modification will the large opening perforated pipe intake discussed in Section IV. It result in a reasonably uniform inflow and will permit convenient cannot be placed at a remote offshore location inaccessible for handling for the specific type of wall. mounted screen to which periodic removal and cleaning. this discussion applies. Tests to date have shown that the 4
- 2. Backwash piping and valving is relatively complex for a large array maximum inflow velocity for this design will be about 125 percent of the average, j of screen units. Also, the screen and guide materials tend to be j c.
more costly than for standard screens. It is possible that these To size the pipe leading from the screen unit into the pump chamber.
5 factors will negate much of the economic advantage of the elimina- assume a maximum outlet velocity of about 5 fps (1.5 m/sec). Tests i <
tion of trash bars and traveling screens. date indicate that the flow into the screen will be uniform when this design procedure is used.
- 3. Intakes proposed to date for water quantities up to say 50.000 gal / min (200 m3 / min) require a large number of relatively small screen units d. The end plate of the screen unit may be either closed with a resulting in a total structure size greater than that utilizing solid plate or with additional screen material. There is conventional screens. The intake can undoubtedly be designed for evidence that air blast backwashing is more effective if the substantially larger quantities of water, but the screen units
- end plate is solid.
must be larger than any proposed to date and handling and cleaning e. Physically locate the screens to allow for at least 24 in, will be more difficult. u (61.0 cm) of head loss from the inlet system to the pump chamber.
- 4. The small-opening screens have not to date been proven suitable for including losses through the screen itself, the piping and the all water qualities. Until more substantial test and operational ; volving.
This will allow for kaad loss buildup between cleaning
, data become available, preinstallation testing is recommended for . W adons.
each site. This will include biological testing. corrosion testing. . f. Determine the total area Jf the screen by assisning an opaning and the testing of the screen system as a whole, with regard to l { width based on the biological requirements and assuming a wire
) spacing of screen units to avoid interference under specific site ; f ze from the manufacturer's catalogue. For example, a typical waterway flow Conditions. I
- I a
I l
i*
I
r .
e gg W AT E R INT AK E ST RUCTURES .
, SCREENING FOR ORG ANISMS 139
- profile wtre size is 0.069 in. (1.75 rn) wide on the front face.
For this w6re typical percent openings would be as follows: _
/ b N% l TABLE V-2 ,
&( ll $ !.. . . p, l ."
OPEN AREA VERSUS WIOTH OF OPENING FOR 0.069 INCH PROFILE WIRE <o be 1 l H.
W t o t h o f_ _Open_ing Perc ent of_.Open_A_rea.
0.02 in. (0.5sm) 221 0.04 in. (1.0 en) 16 ,, c...c.s
, v_ ,,
= . + ."..
0.06 in. (1.5en) 46 .- -
0.08 in. (2.0 en) 53 8
' l! I I j ... . e. .f Provide at least one more screen unit than called for based on total -l- - }--
- 1 d
9 . .. _ L. s=
1 area required. Yhts will pemit maintaining the desired flow area ,
~
l with one unit out of service for backwashing or manual cleaning. .. ,, ,,,,. ,,
e t Provide suitable valving and piping to permit isolation of each
-h I s5_ _ [
1 unit separately for backwashing or removal. -
r- .. _.
- h. Provide an air backwash system. l
.. J l l ,
[~-'- ' l ] --- - sar
- l. Space the screens at least twice the diameter of the screen apart , _ _
a
,, , _ _ ., , , ! 9 i to avoid mutual interference of the flow fields approaching the . .
- ; ,,, .;_j ! i screens. - - s .. t
= .
.- ~
, s ,s l t
- B 5 Fig. V-6 15 a typical chart fo'r sizing one type of small-opening cylindri-
'l- - M M cal screen unit designed for an average inflow velocity of about 0.34 fps .. .. .
_# i i sia i -
e 6
j (0.10 m/sec). The chart also lists weights for single screen units. This g
", ,I, ,
chart is applicable only for No. 69 profile wire. Similar charts can be ,,, ; 4;
' obtained from manufactur ers for other wire stres and screen configurations.
- STANDARD SINGLE SCREEN DIMENSIONS & WEtGHTS MISCELL ANEOUS PilV5ICAL EXCLUSION CONCEPT 5 pani ssuneen *7* O'O L D L 7%.oss' enou sia 12 e4 ss Other less prantstng physical exclusion systems have been studied exten, sively and are still being investigated. Among these are the following
- ; 51s is la no
" 'O '3'
- a. Artificial filter beds. Fig. V-7. Engineering problems have to
#3 '80 date not been resolved for large and n.11y reliable water with. I l 24 25 2m drawals f rom such filters (15). The primary problem with artift-
, 27 29 320 cal filters is their potential for plugging and the associated m M 32 4lo difficulty of providing a reliable backwash system. There are a ;
i M sos few reasonably successful small installations associated with 38 595 water supply withdrawals from clear water sources. , , , , ,
l Figure V-6 PROFILE WIRE SCREEN CHART i
, Courtesy of: Johnson Division UOP Inc.
f I
l h t