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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
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PHILADELPHIA ELECTRIC- COMPANY 2301 MARAET STREET P.O. BOX 8699 PHILADELPHI A. P P 19101 (319) 641 5005 JOSEPH W. G ALL AGHER
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SEP 151988 Docket Nos: 50-277 tir. C. E. Rossi, Director 50-278 Division of Operational Events Assessnent Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Ccmnission Attn: Doctsnent Control Desk Mall Station P1-137 Washington, DC 20555
Subject:
Peach Bottcrn Atomic Power Station (PBAPS) Units 2 & 3 tRC Bulletin 88-05, dated May 6,1988 "tbnconforming Material Supplied by Piping Supplies, Inc. at Folsem New Jersey and West dersey Manufacturing Ccrmany at Williamstom, New Jersey" Supplement I to Bulletin 88-05, dated June 15, 1988 Supplement 2 tc, Dulletin 88-05, dated August 3, 1988
Dear Mr. Rossi:
The subject NRC Bulletin, received by Philadelphia Electric Ccrmany (PECo) on May 18, 1988, and Supplements 1 and 2, received on June 22, 1988, and August 5, 1988 respectively, require holders of operating itcenses to provide a written response within 120 days of receipt of the Bulletin.
The original Bulletin Instructed licensees to: review purchasing records for suspect noterials, assure that rnatorials ccumly with apolicable codec, or are suitable for their Intended service, or replace such rnaterial .
Subseque.ntly, Supplement I reduced the scope of the review, establishest tirne frrrres for the testing program, and irrposed additional reporting requirements.
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8809200358 880915 PDR ADOCK 05000277
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Supplement 2 temporarily suspended activities such as: document review, in-situ testing, and developnent of Justifications for continued operation (JCO's) until further notice.
The enclosed report comprises our complete response to the specific actions dellneated by Bulletin 88-05 and the subsequent supplements.
The report sumiarizes the docurent review, testing and analytical phases of the 88-05 progran, specifles the various actions undertaken and to be undertaken during each phase, and comlles the results of the document review perfonned prior to the receipt of Supplement 2.
Although the record review was in progress, we did not begin the testing phase prior to the receipt of Supplement 2. Like nuny other plants of the early 1970 vintage, PBAPS was designed and Installed to P31.1/31.7 Code. 'ihe B31.1/31.7 Code does not have the stringent traceability and tracking programs currently required by the ASME Code, i
This hindered record search and delayed the inclementation of the !
testing program. Attachnent I to the report contains the results of the docunentation review.
If you have questions or require additlnnal Information regarding our NRC Bulletin 88-05 program, please do not hesitate to contact us.
Sincerely, l
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Enclosure:
Report J
Copy to: Addres,,ee W. T. Russell, Region 1 Administrator
- T. P. Johnson, US NRC Senior Resident Inspector ,
T. E. Magette, State of Maryland l I
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COWONWEALTH OF PEM4SYLVN41A COUNTY OF PHILJOELPHIA SS.
J. W. Gallagher, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Ccmpany; that he has read the foregoing response to NRC Bulletin 88-05 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, Infornvition, and bcI lef.
hv bhb Vidcf resident O Subscribe Before rne and this sworn /f %day of Septmber,1988.
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'tbtary Publ Ic WELAN1E R. CAMPANELtX Notary PhWk, PMadet;hia, Pmbts!phia Co, Wp Ca*Wtbtn EzMt FebNe'y 12.1990 l
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PEACH BOTTOM ATCNIC POER STATION (PBAPS) i UNIT 2 & 3 RESPO4SE TO NRC BULLETIN 88-05 l
1 DOCKET No. 50-277 50-278
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SEPTEMBER 2, 1988 !
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PEACH BOTTOM ATOMIC F NER STATION UNITS 2 & 3 RESPONSE TO NRC BULLETIN 88-05 PURPOSE:
This report provides a cormlete response to the requirements set forth by NRC Bulletin 88-05 and Supplements 1 and 2 to the Bulletin.
The Bu',locin 88-05 required licensees to review purchasing records to de'. ermine presence of rnatorials supp1Ied by Piping Supplies, Inc.
(PSI) and West Jersey Manufacturing Comany (WJM), provide assurance that PSI and WJM supp11ed rnatorials rneet the appIIcable codes and specification requirements or are suitable for their Intended service, or replace unsultable rnaterials.
This report Is Intended to fully satisfy the 120-day written response reporting requirements of NRC Bulletin 88-05 as rrodified by Supplements 1 & 2.
SUFf%Ry:
In response to the Bulletin and Supplements 1 and 2 requirements, Philadelphia Electric Canpany (PEco), in accordance with Nuclear Management and Resources Couric!) (tM MRC) guidelines, developed a three-phased program for Peach Bottan Atcmic Power Station (PBAPS)
Units 2 & 3.
During Phase I of the program, PEco conducted an extensive review of purchase records for PBAPS Units 2 & 3 to determine presence of material supplied by PSI and WJM. We have concluded that suspect rnaterlat has been received at PBAPS Units 2 S 3. Upon discovery of suspect material, those corponents determined to be In the warehouse were irrmediately segregated and placed on hold. Those ccmponents determined to be Installed and accessible In safety-related systems were to be tested in accordance with the Testing Program (Phase II) developed under fM MRC guldelines. However, Supplement 2 suspended in-situ testing before testing could begin for suspect rnatorial identlfled l l as installed and accessible in safety-related systems.
Attactment I to this Report sumiarizes the results of the docunent review conducted until August 5, 1988. It contains the rnatorial database formatted by PU%RC in response to the Bulletin reporting requirements. i i
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Stif>ARY DESCRIPTION OF PBAPS UNITS ? 8 3 NRC BULLETIN 88-05 PROGRN4:
The Peach Bottcm Atcmic Power Station Units 2 & 3 NRC Bulletin 88-05 Program is a three-phase prxjram which addresses the following:
Phase I: Doctmentation Review Phase !!: Testing Phase III: Analysis of Test Results and Development of JustIfIcatton for Continued Operation (JCO's) 00Ctr4ENTATION REVIEW:
(1) Review purchasing records for material purchase of PSI and WJM manufactured / supplied fittings and flanges.
(2) Review maintenance request forms (MRF) for purchase of PSI /WJM material.
(3) Review nodification packages (Mod) for use or purchase of PSI /WJM material, (4) Review Receipt inspection and Storage Reports (RISR) for i PSI /WJM material.
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- (5) DeterTnine Installation status (i.e., location, accessibility, etc.,) via a review of Mod packages, spool Installation records and other pertinent Installation docunentation.
TESTING PROGRNi:
(1) Develop site r.,pecific in-situ testing guidelines in accordance with FU %RC developed guidelines.
(2) Conduct testing of accessible safety-related suspect material.
N4ALYSIS C JCO's:
(1) Analyze results of testing to determine acceptability of ccmponent.
(2) Write qualitative JCO's for those ccmponents that have failed or have been deterinined to be inaccessible.
The program was developed and monitored In accordance with existing Internal PECo procedures and guidelines established by tU MRC for Bulletin 88-05. l The following discusses hcw the progrrm satisfles the required l action items to be undertaken by the IIcensee. To assure clarity, I the requested actions are restated belcw along with PECo response to l each of these Itets.
RESPONSE TO BULLETlH & SUPPLEMENTS 1 Ato 2 REQUIREMENTS:
(1) Actlon Requested Review purchasing records to determine whether any PSI or WJM supplied ASME Code or ASTM material has been furnished.
Supplement I reduced the scope fr m "materlats" to "fittings and flanges". SuppleTent 2 Identified another affiliated ccmpany, Chews Landing Metal Manufa::turers incorporated (CLFO who may have supplied suspect materials.
PECo Response (1) PEco was in the process of reviewing purchasing records for fittings and flanges which may have been purchased frcm PSI and WJM upon receipt of Supplement 2. The results of the partial review were incorporated into the material database established by NWARC. Attachment I provides the results of the docunent review.
Phase I of the PBAPS Units 2 & 3 Bulletin 88-05 Progerm provides the docunentation review. Since Peach Bottcm is designed and Installed to the B31.1/31.7 Code, we encountered several irrpediments associated with traceability of the material.
However, a procedure was developed which addresses the various means by which PSI and WJM materlat may have been procured for use at PBAPS. The docunentation review was divided into the following three (3) categories:
A) Review of Purchase Orders B) Review of Modification (Mod) packages and Malntenance Recuest ForTns (MRF's)
C) Skid Mounted Corponents and Secondary bupp11ers The review, thus far, has identified 267 cenponents that were purchased for Peach Bottcm Atcmic Power Station Units 2 and 3 >
during the time frame (1976 to present) established by the bulletin. NUMARC, acting on behalf of the Industry, coordinated the review for skid nounted ccmponents or those supp1 ted by secondary suppliers. Recently, NUr* ARC provided the Ilst of secondary suppliers and ccuponents purchased to affected utilities. Mcwever, we have tenporarily suspended the docunentation review until further notice frcm the tRC.
(2) letion Requested For ASPE Code and ASTM materials furnished by PSI or WJM that are either not yet installed in safety-related systems at your facility or are installed in safety-related systens of plants under construction, the folicwing actions are requested: (perform action a and either action b or c).
- a. Provide a list of WJM and PSI supplied materials that are found not to be in confnrmance with the appilcable code requirements or procurement specifications and Identify the applications in which those materials are used or will be used. Include the material specification, the nature of the ccrnponent (e.g., pipe flange), size and pressure rating; also Indicate the chain of purchase, and either,
- b. Take actions that provide assurance that all recolved materials ccrmly with ASMC Code Section Ill, ASTM, and appilcable procurement specificaticn requirements, or that demonstrate that such noterials are suitable for the Intended service. For exanple, this program should include specific verification that austenitic stainless steels have been received in a non-sensitized conditlon, or,
- c. Replace all questionable fittings and flanges with materials that have been manufactured in full ccrm11ance with ASME Code Sect!on til, ASTM, and the applicable precurement specification requirments.
Supp1 ment I reduced the scope of the review frcm "materials" to "fittings and flanges".
PECo Response 2a. PEco is a participating morder of the FM%RC 88-03 Prog ram. The FU MRC program estabitshed the scope of the docurentation review, determined testing priorities for operating plants, and issued acceptance criterla for testing to be used by the Industry to ccrmly with the Bulletin's requirerronts.
PUWRC develeped a generic forTrut for the material database to be used by all nurber utilities. The database includes several fields designating material specification, nature of ccrponent, size, pressure rating and chain of purchase.
Attactment I contains the results of our docurentation review conducted until August 5, 1988
- 26. In accordance with NU %RC guidelines, we have developed a well definec, quality assured, testing program to d monstrate conforriunce of suspect material to appilcable codes or to determine acceptability of the suspect material.
In additico to the generic material database, fM MRC also created a generic testing database for industry use.
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.- Severai guidelines estab11shed by NtJ%RC and accepted 15y the NRC include:
- Use of the Equotlp Hardness Tester for in-situ hardness testing of flanges and fittings.
- For operating plants, fleid testing priority to be placed on flanges and fittings Installed and L
accessible on safety-related systems.
a Supplement 2 terrporarily suspended all fleid activities prior to irrplorrentation of our testing program.
2c. The actions described in 2b above preclude any replacement of questionable fittings and flanges.
Additionally, PECo will not Install ccrmonents which are suspect. A hold was prctnptly placed cn suspect components in the warehouse mtl1 further notice frcm the NRC.
(3) Action Requested For ASPE Code and ASTM materials furnished by WJM.or PSI already Installed in safety-related systems in operating plants, the following actions are requested:
- a. Provide a list of the WJM and PSI supplied materials l that are found not to be in confonnance with the I appilcable code requiretrents or procurertent specifications and identify the appilcations in which l
the materials are used. include the rmterial specification, the nature of the cormtnent (e.g., pipe flange), size, and pressure rating; also Indicate the chain of purchase.
- b. Take actions requested in 2b or 2c above. Hcwever, an evaluation should be undertaken prior to replacing L questionable material in accordance with 2c above that !
I considers the occupational radiation exposure that would >
be received during the replacment process. This i evaluatico should be considered in developing the
,' rnethod and timing of material replacem)nts.
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- c. Docurent and reintain for inspection a basis for :
continued plant operation if the program requested in item 3b has not been ccrrpleted within 120 days of the date of roccipt of this bulletin.
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< Supplement 1 reduced the scope of paragraph 3 of Bulletin 88-05 from ASME and ASTM "materials" to ASME and ASTM (
"flanges and fittings". For ASME and ASTM flanges and i flt'Ings furnishad by PSI and WJM already Irstalled in 2 safety-related systems in operating plants, ' he fo11cwing i 1 actions are requested by Supplement 1: ;
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- a. Coninence appropriate testing of accessible flanges and t fittings prct@tly to identify conformance of materlats (
' to ASME and ASTM material specifications. Test results
- for flanges and fittings reported to be fran the same j
heat should be ccrnpared for consistency and for i conformance to the ASME/ ASTM specifications and to l
values IIsted on material CbnRs. Any deviation from (
the specification requires an appropriate analysis i justifying continued operation. l i
a b. If any inaccessible flanges or fittings are Identified, !
an analysis must be perfonned justifying continued ,
operation. l l c. All other provlslons of paragraph 3 of Bulletin 88-05 l
{ remain in effect. !
I Supplement 2 termorarily suspended the above llSted [
jL activities. l l
PECo Response !
3a) As stated in item 2 above, we have developed a list of j suspect materials. The conformance of suspect f
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materials to the appilcable material specification was to be deterintned via the testing program. Thus far, we
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I have developed a well defined, quality assured, testing j i program for in-situ testing of suspect materials in
! accorc'ance with existing Internal PEco procedures i and generic N W RC guidelines. Attactynent I contains !
the material data which will be transmitted to tu%RC ,
j soon. i 3b) Due to the difficultles encountered during the record i e review chase, we have not determined the Installation !
3 status of the suspect items.
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3c) Phase III of the PBAPS 88-05 Program addresses development of JustIfIcatton for continued operatlon. '
If JCO's are needed in the future for Bulletin 88-05, we will develop and maintain them for inspection. ;
l (4) Action Requested l
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For any PSI and WJM suppiled materidis having suspect CMTRs I and used in systems that are not safety-related, take -
l actions ccnnensurate with the function to be performed.
! Supplement 1 provides the following further Instructlons:
} For flanges and fittings already identifled as having been i supplied by PS! or WJM, the actions requested in 3a and 36 l
< above are to be ccric1sted within 30 days of receipt of this supplement. For flangos and fittings identified after
- receipt of this supplemer:t, the actions requested in 3a and - l 1
3b above are to be empleted within 30 days of identifying the flanges or fittings as being supplied by PSI and WJM. l F
- Supplement 2 temporarily suspended the ~ 'e listed .
activities for operating plants.
j PEco Response We did not begin our testing phase because of the difficulties encountered during the docurentation review phase. A higher ,
priority on safety-related systems would have precluded any testing on non-safety-related suspect flanges prior to the !
conviction of the safety-related flanges. l
) (5) Action Requested 4 e
} Addressees are recuested to retain nonconforming materials !
i and mnintain for inspection the docuncntation of the l specific actions taken for the identified meterials untti !
l advised further by the NRC. Honconfonning materials should be i t
segregated to ensure that they are not inedvertently used. f 3 PECo Resperg , i i' !
We have segregated and retained the susrect nuterials as [
, requested above. Docurlentation pertaining to the specific [
{ actions undertaken for the Identifled materials will be i maintained for inspection. i 1 P I
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(6) Action Requested l
For operating plants, all scheduled actions should be !
ccnpleted before a restart from the next major outage starting after 180 days fran the date of recelpt of this bulletin. For plants under construction all scheduled actions and the reporting required by 2 below should be ccrpleted prior to the planned fuel load date. If any addressee camot meat this schedule, they should Justify to !
the NRC their proposed alternative schedule. j Supplements 1 & 2 further instruct:
Addressees are encouraged to report the results of tests of l PSI and WJM supplied flanges and fittings to the INPO i Nuclear Network for dissanination to the Industry.
PE0o Response The nuterial database is being transmitted to NUMARC.
This report satisfies the required 120 day written response requested by the NRC.
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Recordt PLfv6 Lht? I:!E,1 TRMS RD#K 1 Ft#S . 02 4 3 sets
, 2 PMOS 01 A 3 sets - 1 set returred - 2 sets accepted en R.I.R. cated 5/2i/87 12 fourd in ,
3 PMPS 01 4 0.C. hold area, addt'l Heat codes fourd ? B39 4 472892 4 PMPS 03 A 2 sets - Canuto C of C states Heat Ccces of B34 9 PM4 OS A 2 sets 6 PM>S 06 A 2 sets 7 PMPS 08 A credit from field = 2; R.I.R. cated 3/17/88: roterred 2 to W.J.M. on 2/24/68 8 IMPS 16 A 2 etts 9 PMCS 18 A cor<streetion R.I.R. ststes beat f(IH) 10 DEWS 19 A purc*ated fer HDCI 1AND ca RM9 (K-02)
!! 4AM 20 A purchases for HCCI GLAND SCL ILCWER (K-M) 12 F MDS 21 A purchases for H:Cl GLAND SCA K04R (K-02) 13 FS&$ 22 A purchased for HCCI CLMi SCL ILMR (K M) 10 PMPS 14 A 6 sets 19 PLA?S 25 4 8 sets-10 transferes fece Limerick 16 FMPS 26 A e 6 lecates in 0.C. hold area. Heat coce to be verified.
17 4 APS 27 A a 61: cates in 0.C. hold area. heat code to te verifiec.
18 FMPS 32 A e = ho CSTR for itee, Heat coce free R.I.R.
19 MM 33 A kn-0(located in 0.C. held areal % CMTR Iccated M F9-3 34 A %n-0 (lccated in D.C. hold area)No CMTR located 21 Gt4PS 35 4 trro flecated in Q.C. hold area)% CmTR located 12 FESS X A %n-G (located in Q.C. hold areatho CNTR located 23 ctA"5 37 A N4 !!xated in D.C. hold area)% CMTR Iccated i 20 PM?S 38 A F:S=seall torg2e, 7 25 eMM 39 A M5=ssait ton;a.
It CMPS a0 0 Noe-O (!ccated in 0.C. hold arealhe CMTR Iccated l 27 MA?S 41 A Transferred fece Limeriet on 140527,No CMTR Iccated !
28 TMOS 42 A Tra*sferred free Limerick on TFe27,% CMTR located ;
- 29 01 4 43 A Transferred from Limerick on TR*27,% WR locates 30 01 C Ou=.097 ;
31 03 C heat treatment at a sin. 1915ce;.F. Cu=.097 [
32 09 C Cu=.05 l
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