Forwards Info on NUREG-0737,Item 2.F.1.4, Containment Pressure Monitor, Item 2.F.1.5, Containment Water Level Monitor & Item 2.F.1.6, Containment Hydrogen Monitor, in Response to NRC 830105 RequestML20071D805 |
Person / Time |
---|
Site: |
Peach Bottom |
---|
Issue date: |
03/04/1983 |
---|
From: |
Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
---|
To: |
Stolz J Office of Nuclear Reactor Regulation |
---|
References |
---|
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8303110329 |
Download: ML20071D805 (15) |
|
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 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 ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl 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 ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition 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 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 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 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) 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 ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam 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 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 ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC 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 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS 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 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 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 ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather 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 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 ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 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 ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders 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 ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC 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 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS 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 05000278/LER-1999-002, Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER1999-07-12012 July 1999 Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER 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 ML20209D9781999-07-0808 July 1999 Forwards Addl Info to Support EA of Proposed 990212 License Application ECR 98-01675,correcting Minor Administrative Errors in TS Figure Showing Site & Exclusion Areas Boundaries & Two TS SRs 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 ML20209E1131999-06-30030 June 1999 Forwards Proprietary NRC Form 398, Personal Qualification Statement-Licensee, for Renewal of RO Licenses for EP Angle,Md Lebrun,Jh Seitz & Zi Varga,Licenses OP-10646-1, OP-11081,OP-11082 & OP-11085,respectively.Encls Withheld ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209C1201999-06-30030 June 1999 Informs of Util Intent to Request Renewed License for PBAPS, Units 2 & 3,IAW 10CFR54.Licensee Anticipates That License Renewal Application Will Be Submitted in Second Half of 2001 05000277/LER-1999-004, Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities1999-06-20020 June 1999 Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities ML20196A5291999-06-14014 June 1999 Forwards Final Pbaps,Unit 3 TS Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal-hydraulic Stability Solution Hardware ML20195E6051999-05-27027 May 1999 Requests Exemption from Requirements of 10CFR72.44(d)(3) Re Submittal Date for Annual Rept of Principal Radionuclides Released to Environ.Exemption from 10CFR72.72(d) Re Storage of Spent Fuel Records,Additionally Requested ML20195B8171999-05-25025 May 1999 Forwards Final TS Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20195B6191999-05-19019 May 1999 Forwards PBAPS Units 2 & 3 Annual Radiological Environ Operating Rept 56 for 980101-1231, Per Section 6.9.2 of Ol. Trace Concentrations of Cs-137 Were Found in Sediment Consistent with Levels Observed in Previous Years ML20206P9171999-05-10010 May 1999 Updates Some of Transmitted Data Points Provided in Data Point Library ERDS for Pbaps,Units 2 & 3.Data Point Info Format Consistent with Guidance Specified in NUREG-1394 ML20206K6581999-05-0404 May 1999 Forwards PBAPS Bases Changes Through Unit 2 Bases Rev 25 & Units 3 Bases Rev 25.Bases Reflect Change Through Apr 1999, Thereby Satisfying Frequency Requirements of 10CFR50.71 ML20206D4651999-04-29029 April 1999 Forwards Rev 16 to UFSAR & Rev 11 to Fire Protection Program (Fpp), for Pbaps,Units 2 & 3.Page Replacement Instructions for Incorporating Rev 16 to UFSAR & Rev 11 to Fpp,Encl ML20207B8431999-04-23023 April 1999 Forwards Final Rept for 981117,plume Exposure Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific for Peach Bottom Atomic Power Station.One Deficiency & 27 Areas Requiring C/A Identified ML20206C5461999-04-20020 April 1999 Forwards Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2. Revs Made to ODCM & Station Process Control Program (PCP) During Rept Period,Encl 05000277/LER-1999-003, Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding1999-04-16016 April 1999 Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv)1999-04-0808 April 1999 Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities ML20205J0831999-03-26026 March 1999 Requests Enforcement Discretion from Requirements of PBAPS, Units 2 & 3 Ts.Enforcement Discretion Pursued to Avoid Unneccessary Plant Transient Which Would Result from Compliance with TS ML20205B6421999-03-24024 March 1999 Submits 1998 Annual Decommission Rept for Pbaps,Unit 1. There Were No Reportable Events Involving Unit 1 for 1998 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7171990-09-18018 September 1990 Comments on SALP Board Repts 50-277/89-99 & 50-278/89-99. Author Pledges Continued Mgt Support of & Attention to Rate of Improvement,Achievement of Goals & Performance of Routine Activities ML20065D4421990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Proposed Schedules for Operator Licensing Exams, Requalification Exams & Generic Fundamental Exams Encl ML20064A7751990-09-13013 September 1990 Advises That Ba Stambauth No Longer Maintains Need to Hold Senior Operator License ML20065D3741990-09-11011 September 1990 Forwards Rev to Relief Request 10-VRR-2 Re RHR stay-fill Supply Check Valves,Per ML20059F0541990-08-31031 August 1990 Responds to NRC Re Violations Noted in Safety Insp Repts 50-277/90-13 & 50-278/90-13.Corrective Actions: Training Will Be Provided for Personnel Re Requirements of Drawing E1317 & Administrative Procedures A-2 & A-6 ML20028G8181990-08-27027 August 1990 Forwards Peach Bottom Atomic Power Station Semiannual Effluent Release Rept,Jan-June 1990. No Revs Made to ODCM During Rept Period ML20059A6461990-08-15015 August 1990 Responds to Violation Noted in Insp Repts 50-277/90-200, 50-278/90-200,50-277/90-06 & 50-278/90-06 & Payment of Civil Penalty in Amount of $75,000.Corrective Actions:Emergency Svc Water Sys Restored to Operable Status ML20058N1991990-08-0909 August 1990 Advises of Change of Address for Correspondence Re Util Operations.All Incoming Correspondence Must Be Directed to One of Listed Addresses ML20058Q4051990-08-0606 August 1990 Forwards Public Version of Revised Emergency Response Procedures,Including Rev 12 to ERP-140,App 2,Rev 13 to ERP-140,App 3,Rev 4 to ERP-230,Rev 3 to ERP-305 & Rev 3 to ERP-660 ML20058M6631990-08-0303 August 1990 Responds to NRC 890406 Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81.Based on Encl Schedule,Overall Projected Implementation Date Will Be 901119 ML20056A9611990-08-0303 August 1990 Notifies That Be Saxman Terminated Employment & Operating Responsibilities W/Util on 900706 ML20081E1581990-07-30030 July 1990 Forwards List of 1990 QA Program Changes for Plant.List Identifies Page & Paragraph Number,Brief Description & Type of Change ML20056A0421990-07-27027 July 1990 Forwards Updated Human Resource Status Rept for Jan-Jul 1990 for Areas Identified in Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81 ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML20055H8331990-07-20020 July 1990 Submits Change of Addresses for Correspondence Re Util Nuclear Operations ML20044B2621990-07-12012 July 1990 Forwards Annual Progress Rept on Implementation of Control Room Enhancements,Per NUREG-0737.Corrective Actions for All Priority 1 Human Engineering Discrepancies Completed for Unit.Remaining Priority 2 Discrepancies Under Reevaluation ML20055G5481990-07-11011 July 1990 Forwards Public Version of Revised Epips,Including Rev 12 to ERP-140,App 3 & Revs 3 to ERP-310 & ERP-317 ML20043H7041990-06-21021 June 1990 Forwards Endorsements 143-146 to Nelia Policy NF-140 & Endorsements 93-96 to Maelu Policy MF-67 ML20044A2961990-06-21021 June 1990 Submits Revised Response to NRC Bulletin 89-002 Re safety- Related Swing Check Valves to Be Installed on Emergency Diesel Generator.Bolts Will Not Be Replaced Because Valves W/Original Internal Bolts Meet Requirements of Bulletin ML20043H6081990-06-19019 June 1990 Corrects 900427 Response to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing - 10CFR55 & Conforming Amends. ML20055C7621990-06-18018 June 1990 Informs NRC of Plans Re Licensing of Senior Reactor Operators (Sros) Limited to Fuel Handling at Plants.Util in Process of Implementing New Program for Establishment & Maint of Licensed SROs Limited to Fuel Handling at Plants ML20043G8131990-06-13013 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-277/90-06 & 50-278/90-06.Corrective Actions:Surveillance Test 6.16, Motor Driven Fire Pump Operability Test, Will Be Revised ML20043H0111990-06-12012 June 1990 Advises That AR Wargo Reassigned from Operating Shift Responsibilities & Will Be Resigning License,Effective on 900514 ML20055D1141990-06-0808 June 1990 Forwards Public Version of Revs to Emergency Response Procedures,Including Rev 9 to ERP-140 & Rev 3 to ERP-315 ML20043D7351990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-277/90-04 & 50-278/90-04.Corrective Actions:Procedural Controls Strengthened to Preclude Licensed Operators from Performing Licensed Duties W/O Successfully Passing Exams ML20043E9261990-06-0404 June 1990 Forwards Response to 900327 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043D2681990-05-31031 May 1990 Forwards Response to NRC Requests Re PECo-FMS-0006, Methods for Performing BWR Reload Safety Evaluations. Util Core Monitoring Activities Routinely Access Accuracy of steady-state Physics Models Used in Evaluation of Parameter ML20043D6451990-05-30030 May 1990 Responds to NRC 900503 Ltr Re Violations Noted in Insp Repts 50-277/90-08 & 50-278/90-08.Corrective Actions:Glaucoma Testing Program Initiated for Security Personnel & Necessary Equipment to Perform Glaucoma Testing Onsite Obtained ML20055C5491990-05-18018 May 1990 Forwards Response to Request for Addl Info on 900412 Tech Spec Change Request 89-20 Re Postponement of Next Snubber Visual Insp,Due 900526,until Scheduled mid-cycle Outage in Fourth Quarter 1990 ML20055C5121990-05-18018 May 1990 Provides Info Inadvertently Omitted in Re Property Insurance Coverage for Plants.Limerick Generating Station Unit 2 Should Have Been Ref as Being Included Under Insurance Coverage ML20055C4851990-05-15015 May 1990 Forwards Annual Financial Repts for 1989 for Philadelphia Electric Co,Pse&G,Atlantic Energy,Inc & Delmarva Power & Light Co ML20043A3341990-05-14014 May 1990 Advises of Util Proposal to Provide Response to NRC Request for Schedule for Compliance W/Reg Guide 1.97 Re Neutron Monitoring Instrumentation 3 Months After NRC Concurrence W/Bwr Owners Group Design Criteria ML20042E7651990-04-27027 April 1990 Informs That Mod 2285 Completed on Unit 3,but That Mod 2285 Will Not Be Completed on Unit 2 During 8th Refueling Outage ML20042E8931990-04-27027 April 1990 Responds to Violation Noted in Insp Rept 50-278/90-01. Corrective Actions:Automatic Depressurization Sys Logic Sys Functional Tests Will Be Revised to Include Guidance in Unique Application of Test Lights ML20042F3241990-04-27027 April 1990 Advises That Organizational Changes Made in Advance of Approval of Tech Spec Change Request 88-06.Changes Do Not Present Unreviewed Safety Question ML20042E8741990-04-27027 April 1990 Responds to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing. Certifies That Limerick Operator Requalification Training Program Renewed on 900125 & Peach Bottom Subj Program Renewed on 890622 ML20012F4801990-04-0202 April 1990 Forwards Errata to Unit Shutdowns and Power Reductions Monthly Operating Rept for Feb 1990 ML20012F0971990-03-22022 March 1990 Forwards Summary of ASME Repairs & Replacement Completed, Per Facility Second 10-yr Interval Inservice Insps Completed During 900331-891111 Extended Refueling Outage ML20012E2151990-03-20020 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' for Peach Bottom.Response for Limerick Generating Station Will Be Provided by 900504 ML20012C2931990-03-12012 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey, Per 900118 Request ML20012B6211990-03-0808 March 1990 Provides Actions Taken to Ensure & Verify Sys Design Basis Performance,Per 900205 SSFI at Facility ML20012B9011990-03-0606 March 1990 Forwards 870331-891111 Inservice Insp Program Final Rept for Peach Bottom Atomic Power Station Unit 3 1987-1989 Extended Refuel Outage. Several Indications Identified ML20012A2661990-02-26026 February 1990 Forwards Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Tech Spec Change Requests 89-13 & 89-14, Revising Nuclear Review Board Membership & Meeting Frequency & Adding Independent Safety Engineering Group Requirements ML20011F2541990-02-23023 February 1990 Forwards Revs to Physical Security Plan.Encls Withheld (Ref 10CFR73.21 & 2.790) ML20011F3791990-02-21021 February 1990 Provides Revised Schedule for Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 & Explanation Why Jan 1993 Completion Date Cannot Be Met Due to Unavailability of Matls.Intallation Scheduled for Cycle 9 Outage ML20006F5491990-02-16016 February 1990 Certifies That 891122 Tech Spec Change Request (Tscr) 89-15, 891228 Tscr 88-18 & 900214 Tscr 90-04 Mailed to Commonwealth of Pa,Dept of Environ Resources ML20006F1621990-02-15015 February 1990 Forwards Progress Rept Re Implementation of Control Room Enhancements as of End of Seventh Refueling Outage,Per NUREG-0737.Rept Delayed to Allow for Independent Verification of Control Room Enhancement Status ML20012B1731990-02-15015 February 1990 Forwards Public Version of Revs to Epips,Including Rev 5 to ERP-101,App 1 to Rev 13 to ERP-110,App 2 to Rev 10 to ERP-110,App 1 to Rev 7 to ERP-140,App 2 to Rev 10 to ERP-140,App 3 to Rev 11 to ERP-140 1990-09-18
[Table view] |
Text
,
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELt>S L. DALT;40FF
.JM,!"/l5%o, March 4, 1983 Docket Nos. 50-277 50-278 Mr. V. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
NUREG-0737 Item 11.F.1.4 Containment Pressure Monitor Item II.F.1.5 Containment Water Level Monitor Ttem II.F.1.6 Containment Hydrogen Monitor RE: Peach Bottom Atomic Power Station
Dear Mr. Stolz:
The attachment to this letter provides the information on the NUREG-0737 requirements referenced above, as requested in your letter of January 5, 1993 (V. P. Stolz to E. G. Bauer, Jr.,
l PECo.). The information presented'in'the attachment is l designated with a numbering format that corresponds to your
! requests.
Should you have any questions regarding this matter, please j do not hesitate to contact us.
1 i
Sir.cerely, ll ;
Z Jt[
Attachment /-
cc: Site Inspector l
C303110329 830304 I PDR ADOCK 05000277 l p PDR t
3
Docket Nos. 50-277 50-278 Attachment-
SUBJECT:
Request for Additional Information NUREG-0737. Items II.F.1.4, 5 and 6 Peach-Rottom Atomic Power Station Units 2 and 3 (1) Exceptions Being Taken To NUREG-07?7 Recuirements Request:
(la) Please indicat6 any exceptions that you plan to take to the NUREG-0737 itens in our scope of review. For each exception indicate (1) why you find it difficult to comply with this item, (?) how this exception will affect the monitor system accuracy, speed, dependahility, availa'oility, and utility, (3) if this exception in any way compromises the safety margin that the monitor is supposed to provide, and (4) any extenuating factors that make this exception less deleterious than it anpears at f ace value.
Response
( l a ') In addition to the exceptions described in items (3b) and (Ic) of the enclosure to your January 5, 1983 letter, we have taken the following exceptions to the NUREG-0737 requirements for containment pressure monitors, containment water level monitors, and containment hydrogen monitors. These exemption requests were previously identified in correspondence dated December 22, 1980 (S. L. Daltroff, PECo. to D.
G. Eisenhut).
1.) The design and qualification criteria for accident monitoring instrumentation (Appendix B of NUREG 0737) recommends physical separation in accordance with Regulatory Guide 1.75, rev. 2.
Peach Bottom was not designed and built to meet the separation criteria of Regulatory Guide 1.75, and back fitting the facility to this criteria is not practical. We have designed the accident monitoring instrumentation to the separation criteria applicable to the plant as described in the Peach Rottom Final Safety Analysis Report.
This exception does not affect the system's accuracy, speed, dependability, availability, or utility and does not compromise the safety margin that the instrumentaion is supposed to provide.
_.. )
Page 2 2.) The design and gaalification criteria for accident monitoring instrumentation (Appendix B of NURPG-0737) recommends environmental qualification in accordance with Regulatory Guide 1.89 (NUREG-0588). This requirement specifies qualification of new equipment to IEEE Std. 323-1974. The containment pressure transmitters are cualified to IEEE Std. 323-1471 since they were the best available equipment on the market at the time of their purchase. This exception will not affect the accuracy, speed, dependability, availability, or utility of the pressure monitoring system since these transmitters are essentially the same as transmitters from the same vendor that have since been quslified to IEEE 323-1974 requirements. In addition, the worst-case adverse environment at Peach Bottom is much less severe than the environment for which these transmitters have been qualified.
Therefore, this exception does not compromise the safety margin provided by this instrumentation.
3.) Miny of the rogulatory guides 21sted in Appendix B of NUREG-0737 pertainhtg to cuality assurance were not in existence at the time the Peach Bottom hydrogen analyzers were installed.
However, the analyzer system was specified, procurred, designed, fabricated, and installed in accordance with quality assurance programs which complied with the applicable portions of 10CFR50, Appendix B. Therefore, this exception does not affect the system's accuracy, speed, dependability, avai.1 ability, or etility and will not compromisa the safety margin that the monitor is supposed to provide.
Recuest:
(1b) In your letter of 22 Dec. 80 from Shields L. Daltroff (PECo) to Darrell G. Eisenhut (NRC), you state that your water level transducer range will extend to one foot above the bottoz of the suppression pool, rather than to the bottom as is required by NUREG-0737. You further state that you wish to take this exception so that you can use the existing water level transmitter rather than installing a new one. We find this exception to be acceptable, and will not require that you provide any further justification on this point.
t >
$ Page 3
Response
lb) No response required.
Recuest (Ic) In your letter of 23 Dec 81 from Shields L. Daltroff (PECo) to Darrell G. Eisenhut (NRC), you state that your hydrogen monitor has a 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> warmup period, whereas NUREG-0737 reauires that the hydrogen monitor be operation within one half hour after an accident.
Please state Nhat measures have been tried or are going to be tried to decrease the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> warmup period and state what progress, if any, has been made on this problem. You state that the long warmup time can be justified by the fact that you have an inerted containment. Are there any other extenuating factors that justify the long warmup time?
Response
Ic) As stated in correspondence dated December 23, 1981 (S. L. Daltroff, PECo to D. G. Eisenhut), the two hour warmup time of the hydrogen analyzers is sufficient for their intended use. Since the Peach Bottom containment is inerted and post-accident combustible gas control is maintained by oxygen deficiency, the control of combustible gas concentrations in containment is relatively insensitive to the rate or extent of hydrogen generation due to metal-water reaction. Maintenance of containment Qas concentrations below combustible limits is accomplished by the addition of nitrogen to limit oxygen concentration to less than 5%. Indication of hydrogen concentration is used only to determine if a level of hydrogen exists within containment such that control of oxygen concentration is needed. Based on Safety Guide No. 7 (now regulatory guide 1.7) assumptions, approximately one day will c-lapse af ter a loss of coolant accident before nitrogen addition is required. Recent evaluations submitted by the BWR Owners' Groups and reviewed by the NRC staff have demonstrated that the Regulatory Guide 1.7 radiolytic oxygen generation is extremely conservative. (Refer to letter number BWROG-8224 from T. J. Dente of the BWROG to D. G. Eisenhut of the NRC dated June 21, 1982, and the letter from W. G. Counsil of NUSCo to W.
J. Dircks of the NRC dated August 6, 1982.) Therefore, this exception to the NUREG-0737 requirements will not l
-,y , . _ .
__ m - _
Page 4 affect the hydrogen monitoring system's accuracy, speed,' dependability, availability, or utility in ,
performing its intended function. Furthermore, this exception does not compromise the safety margin that the monitor is supposed to provide.
! (2) II.F.1.4 - Containment Pressure Monitoring Syste9 Accuracy and Time Response.
Request (2a) Provide a block diagram of the configuration of
. modules that make up your PMS. Provide an explanation 4
of any details in the block diagram that might be necessary for an understanding of your PMS accuracy and time response.
Response
(2a) See figure 1 for a block diagram of the configuration of modules that make up the containment pressure monitoring system. There are four instrument loops, two with a range of O to 225 psig and two with a range of 5 to 25 psia. The power for the instrument loops l and the power to run the recorders is provided from
! the power supply through the power distribution
, mrdule.
i.
Request:
(2b) For each module provide a list of all parameters which describe the overall uncertainty in the transfer function of that module.
Response
[
(2b) The following parameters describe the overall uncertainty of the containment pressure monitoring system:
l Pressure transmitter (5 to 25 usia range)
Accuracy: + 8.3% (Includes combined effect of linearity,
- hysteresis, and repeat-ability)
Seismic effect: + 0.83%
4'
^
i Page 5 i
Temperature effect: 1 0.89% (for temperature change from 95 degrees F to 149 degrees F) 1 Power supply effect: negligable Deadband: none Stability: 1 0.42%
Pressure transmitter (O to 225 psig range) i Accuracy: i 7.4% (Includes combined j effect of linearity, hysteresis, and repeat-ability)
Seismic effect: + 0.74%
Temperature effect: } 1.0% (for temperature change from 85 degrees F to 149 degrees F)
Power supply effect: negligable Deadband: none Stability: 1 0.37%
Current to Volimge Converter Accuracy: + 0.17%
Power Supply Effect: + 0.016%
Ambient Temp. Effect: [ O.17% (for temperature change from 70 degrees F to 120 degrees F)
Relative Humidity Effect: + 0.17%
Seismic Effect: 7 0.17%
Recorder (recording function)
Accuracy: + 0.25%
Repeatability: 0.1%
Ambient Temp. Effect: < 0.25% (for temperature change from 70 degrees F to 120 degree 9 F)
Relative Humidity Effect: +0.25%, -0.5%
Power Supply Effect: < 0.009%
Recorder (indicating function)
Accuracy: + 0.17%
Repeatability: 5.13 Ambient Temp. Effect: 0.25% (for temperature change from 70 degrees F to 120 degrees F)
Relative Humidity Effect: + 0.17%
Power Supply Effect: 5.009%
NOTE: The above values are expressed as a percentage of full calibrated range.
Page 6 Recuest:
(2c) Combine parameters in 2b to get an overall system uncertainty. If you have both strip chart recorder and indicator output, give the overall system uncertainty for both systems. If you have systems spanning difi;erent ranqes, give the overall system uncertainty for each system.
Response
(2c) The following is the overall system uncertainty:
+7.55% for 0 to 225 psig recorder T7.53% for O to 225 psig indicator T8.43% for 5 to 25 psia recorder IR.41% for 5 to 25 psia indicator Recuest:
(2d) For each module indicate the time response. For modules with a linear transfer function, state either the time constant,)* , or the Ramp Asymptotic Delay Time, RADT. For modules with an output that varies linearly in time, state the full scale response time.
(Most likely the only module you have in this category is the strip chart recorder.)
Response
(2d) The following is the response time for each module:
Transmitter - time constant is 0.2 seconds.
Current to Voltage Converter - when excited by an 90%
input step from 10 to 90%, the maximum time required for the output of steady state value is 37 milliseconds nominal and 50 milliseconds maximum.
Recorder - 3.5 seconds to travel from 10 to 90% of the scale.
(3) II.F.1.5 - Containment Water Level Monitoring System Accuracy Recuest (3a) Provide a block diagram of the configuration of ,
modules that make up your WLMS. Provide an explanation of any detalles in the block diagram that
5 I Page 7 might be necessary for an understanding of your WLMS accuracy.
Response
(3a) See figure 2 for a block diagram of the configuration of modules that make up the suppression pool water l 1evel monitoring system. There are two suppression j pool wate: level instrument loops, each with a range of 1 foot to 21 feet from the bottom of the suppression pool. The power for the instrument loops and the power to run the recorde s is provided from the power supply through the power distribution module.
Request:
(3b) For each module provide a list of all narameters which describe the overall uncertainty in the transfer function of that module.
Response
(3b) The following parameters describe the overall uncertainty of the suppression pool water level monitoring system:
Response
Level Transmitter Safety Function Performance: + 3.3% (includes combined effect of non-linearity, deadband, hysteresis, and repeat-ability and the accumu-lative effects of temp.,
radiation, seismic, and LOCA)
Power Supply Effect: + 0.003%
Current to Voltage Converter Accuracy: + 0.17%
Power Supply Effect: T O.016%
Ambient Temp. Effect: I O.17% (for temperature l
change from 70 degrees F to 120 degrees F)
Relative Mumidity Effect: + 0.17%
Seismic Effect: 7 0.17%
Recorder (recording function)
Accuracy: + 0.25%
Page 8 Repeatability: 0.1%
Ambient Temp. Effect: < 0.25% (for temperature
, change from 70 degrees F to 120 degrees F)
Relative Humidity Effect: +0.25%, -0.5%
Power Supply Effect: < 0.009%
Recorder (indicating function)
Accuracy: + 0.17%
Repeatability: 0.1%
Ambient Temp. Effect: 0.25% (for temperature change from 70 degrees F to 120 degrees F)
Relative Humidity Effect: + 0.17%
Power Supply Effect: 5.009%
Indicator Accuracy: + 0.5%
Hysteresis: T 0.67%
NOTE: The above values are expressed as a percentage of full calibrated range.
Request:
(3c) Combine parameters in 3b to get an overall system uncertainty. If you have both stripchart recorder and indicator output, give the overall system uncertainty for both systems. If you have systems spanning different ranges, give the overall system uncertainty for each system.
Response
(3c) The following is the overall system uncertainty:
+3.40% for the recorder
~+3.37% for the indicator on the recorder
+3.45% for the separate indicator (4) II.F.1.6 - Containment Hydrogen Monitoring System Accuracy and Placement Recuesti j (4a) Provide a block diagram of the configuration of modules that make up your HMS. Provide an explanation of any details in the block diagram that might be necessary for an understanding of your HMS accuracy. '
Page 9 If you have different types of HMSF give this information for each type.
Response
(4a) See figure 3, for a block diagram of the configuration of modules that make up the containment hydrogen monitoring system. There are four instrument loops, each with a range of O to 20%. Two loops monitor hydrogen in the suppression pool airspace and two loops monitor hydrogen in the drywell atmosphere.
Recuest:
(4b) For each module provide a list of all parameters which describe the overall uncertainty in the transfer function of that module.
Resoonse:
(4b) The following parameters describe the overall uncertainty of the containment hydrogen monitoring system:
Hydrogen Analyzer Accuracy of Analyzer: + 1.0% (unadjusted for moisture or steam dilution within the containment)
Temperatute Effect: none Flow Measurement Effect: none Power Supply Effect: none Deadband: none Hysteresis: none Recorder Accuracy: + 0.17%
Deadband: 0.083%
Indicator Accuracy: + 0.5%
Hysteresis:
[ 0.67%
Request (4c) Combine the parameters in 4b to get an overall system uncertainty. If you have both strip chart recorder
Page 10 and indicator output, give the c-rerall system uncertainty for both systems.
Response
(4c) The following is the overall system uncertainty:
+ 1.0% for the recorder
} 1.3% for the indicator Recuest:
(4d) Indicate the placement and number of hydrogen monitor intake ports in containment. Indicate any special sampling technioues that are used either to examine one region of containment or to assure that a good cross section of containment is being monitored.
Response
(4d) Redundant analyzers are provided to monitor hydrogen concentration in each drywell and torus. Samples are withdrawn through primary containment penetrations at the following elevations:
drywell: El. 127'-2" drywell: El. 199'-9" torus: El. 125'-0" torus: El. 114'-0" Since the primary containment is not compartmentalized, except into drywell and torus, multiple sample points within the containment compartments for each analyzer are not considered necessary. An analysis of the effectiveness of combustible gas mixing within the PBAPS primary containment is included in FSAR Supplement I, Response to Question 14.6.
Recuest:
(4e) Are there any obstructions which would prevent hydrogen escaping from the core from reaching the hydrogen sample ports ouickly?
Page 11
Response
(4e) There are no single obstructions which can prevent hydrogen escaping from the core from reaching the hydrogen sample ports quickly. Redundant sample lines are provided to ensure that blockage of-a single line will not prevent the analysis of containment gas from either the drywell or the suppression pool airspace.
0 4
t l
i M
O R O O R T
HA L TC O I R D T N N I O C
l
~
~'
G
- N
~ _ I R
" M O "D O T R O I E R N T O R G M
~~
E N
~ V N Y I E N O L D R 1 OO I P A U TC T P R E S E I l i If I II I U l i I l E R S R TE B S W P E U NG UE O S R G EA RRL R P P I RT ETU E E F RL WSD W L T UO OIO O B N CV PDM P A E C M N
. - I
_ - A
_ - T N
- O K _ C
._ O
"A
_ I M' D
_ L
" I U
T R ET O RI T
~
L PT E
2 c l
M A
t m
J
'a
~,
n L
t M
J
i
~ ~ ~
LEVEL CURRENT TO RECORDER TRANSMITTER ---
VOLTAGE y- WITH CONVERTER INDICATOR g
i j l 1 l POWER I DISTRIBUTION I INDICATOR MUDULE L- (See Note) 1 I I I I POWER I SUPPLY I- - - - - - . - - . - - INDICATOR l
(See Note)
POWER i :
I REMOTE
%-REACTOR --* *--CABLE SPREADING-h-CONTROL----->=- SHUTDOWN --N BUILDING ROOM ROOM PANEL l.
J Note: Only one of the two instrument loops 1
have these additional indicators
\
SUPPRESSION POOL WATER LEVEL MONITORING SYSTEM i
i I
FIGURE 2 I
e e
=
a l
.}
.i i
HYDROGEN _. _ ._ _. _ . ._ _.
ANALYZER l INDICATOR I I l
POWER !
I l
I t
- I_ _ _.i RECORDER I
t I I
POWER
- l 4--REACTOR BUILDING-><---CONTROL ROOM-->
l .
{-
L i
CONTAINMENT HYDROGEN MONITORING SYSTEM l
i L FIGURE 3 i
1
_ _ - __ _ _