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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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1 )
PHILADELPHIA ELECTRIC COMPANY 23o1 MARKET STREET
, P.O. BOX 8699 PHILADELPHIA A. PA.19101 l l mm 84140oo
'May 25, 1989 Docket Nos. 50-277.
50-278 j i
U.S. Nuclear Regulatory Commission Attn: Document Control Desk :
Washington, DC 20555 .
SUBJECT:
Peach Bottom Atomic Power Station, Units 2 and 3 l Special Electrical Team Inspection 1 50-277/89-07 and 50-278/89-07 :
REFERENCE:
(1) Letter from J. Strosnider (USNRC) to C. A. McNeill, Jr. (PECo), dated April 20, 1989 (2) Letter from S. J. Kowalski (PECo) to U. S. Nuclear Regulatory Commission, dated March 17, 1989 l
l
Dear Sirs:
The_ purpose of this letter is to forward for your use a complete copy of the eight individual attachments to our advance response to the Special Electrical Team Inspection (Reference 2) as .
requested by the Reference 1 letter. We are sorry you did not I receive the attachments and also regret any inconvenience our delay in; responding to your letter may have caused.
If you have any further questions regarding our response to the inspection, please do not hesitate to contact us.
i Very truly yours, ;
1 G. A.
f.
Hunger, Jr.
Director !
Licensing Section j Nuclear Support Division ;
i
-Attachment ;
l 8906050043 890525 #
PDR G
ADOCK 05000277 PNV
/g/
j l
f lC h....- DocumsntfControl'Dask'
< May 25,'.1989' Page 2 i
cc:- . J. Strosnide'r, Chief, Engineering Branch, Division of Reactor Safety, Region I,.USNRC.
Wi T.; Russell,~ Administrator, Region 1, USNRC LT. P. Johnson, USNRC Senior Resident Inspector
. T.'E. Magette, State of Maryland-J. Urban, Delmarva Power R..A. Burricelli, Pub.ic Service Electric & Gas H. C. Schwemm, Atlantic Electric T.-_M. Gerusky, Commonwealth of Pennsylvania l;
kW
_ . _ . . _ _ _ . . m .a. _.-.._ +_u __ ,.-_c- 4..e._ _e.-a.e.. ._ _ .__.s.___.._ _ _ _ _ _ _ . _ _ _ _ _ - .- _ _ _ _ _ _ _ _ _ . _ _ _ - - _ _ _ . _ _ _ _ _ -._____m_-__---__----_m-.u_______._.___.______-
. s Attachment 1 TITLE: VOLTAGE ADEQUACY AT DC MOV's PECO INTERPRETATION OF CONCERN Several potential operability problems resulting from design deficiencies in power supplies for safety related DC motor operated valves have recently been identified.
The NRC Information Notice No. 88-72 entitled, " Inadequacies in the Design of DC Motor Operated Valves", was issued to inform utilities of the potential problems in the design of dc motor operated valves, it was expected that recipients would review the NRC Information Notice for applicability to their facilities and consider actions as appropriate. At the time of the NRC Special Electrical Team Inspection, PECo had not completed its review of NRC Information Notice No. 88-72.
More recently the NRC issued NRC Information Notice No. 89-11 entitled, " Failure of DC Motor Operated Valves to Develop Rated Torque Because of improper Cable Sizing."
Subsequent to the NRC Special Electrical Team inspection, N'iC Information Notice No. 89-16 entitled " Excessive Voltage Drop in DC Systems" nas issued. This notice extends the concern of adequate voltage beyond DC motor operated valves.
PECO RESPONSE INPO SER 25-88 is related to NRC Information Notice No. 88-72. Both of these documents and NRC Information Notice No. 89-16 were received and are being tracked in the Operating Experience Assessment Program.
The PECo position on issues of INPO SER 25-88 and NRC Information Notice 88-72 have been defined. It has been determined that a design review of dc motor operated valves is required and includes the following activities:
A. Confirmation of the electrical design of MOV's in PBAPS Unit 2.
B. Confirmation of the electrical design of MOV' sin PBAPS Unit 3.
To support the Unit 2 restart activities, item A has been evaluated as described below. Item B will be completed prior to restart of the Unit 3. i To evaluate the electrical design of dc motor operated valves in the PBAPS Unit 2, calculations were performed to address the capability of each valve to accomplish the required safety function under the minimum anticipated dc power distribution i system voltage combined with elevated temperatures resulting from postulated design basis accidents.
1 This evaluation, which incorporated the concerns presented in NRC Information Notice 89-16, indicated acceptable operability of dc MOV's with the exception of the following valves:
MO-2-23-014 MO-2-23-019 MO-2-23-020 For these valves the results of the calculations indicate that the motors, which utilize 1
l step starting resistors, may not actuate their associated valves immediately under the applicable limiting case system and environmental conditions. It was concluded 1
. . . Attachrnent 1 q u
that the installed resistors do not allow the motors to draw sufficient starting -l current and thus the motors may not produce the torque required for timely valve actuation.
To resolve this potential problem a modification to remove the starting resistors from the motor circuits of these valves will be implemented prior to the PB APS, Unit 2 restart. A similar evaluation will be performed for the dc MOV's in Unit 3. Any required modifications will be implemented prior to Unit 3 restart.
PECo will formally address NRC Information Notice No. 89-11 as part of our Operating Experience Assessment Program. However, our existing evaluations-indicate that the PBAPS Unit 2 design, with the modifications mentioned above, does provide the required torque for operability of DC MOV's.
For NRC Information Notice 89-16 a program will be established and calculations performed to confirm voltage adequacy at equipment terminals for non - MOV Class 1E equipment. The results of this program will demonstrate that the voltage drop in power circuits will in no case result in the terminal voltage less than required for equipment operation. Calculations for the operation of dc powered equipment will be prepared to confirm operability of the equipment during design basis conditions.
The cable voltage drop analysir for dc control circuits will include the inrush current of any connected devices, circuit totallength accounting for the cumulative effects of cable cor$ductors, circuit resistance and the device minimum vo!tage rating. The calculations for Unit 2 will be completed in 1989. The Unit 3 calculations will be completed in 1990.
The anticipated impact of this evaluation on PBAPS Unit 2 is considered minimal and does not present a constraint for restart as:
1)
The batteries have been shown to have substantial positive margin, This margin equates to a higher minimum battery terminal voitage throughout the battery duty cycle.
- 2) Cables at PB APS have been sized in accordance with ICEA and NEC criteria providing margin for concerns such as voltage drop while meeting equipment minimum voltage ratings, and
- 3) No dc equipment failures have been identified over the operating history that are attributable to insufficient terminal voltage.
t 2
o -
W' 1l ' ,
l- '
( Attachment 2 TITLE: QUESTIONABLE MARGIN OF 28 AND 2D BATTERY I
PECO INTERPRETATION OF CONCERN Site Question for Engineering SOE P-50080, which is the most recent evaluation of
< the capacity of batteries 2BD001 and 2DD001, concludes that these batteries have a design margin and aging factor of 1.0 and 1.15, respectively. IEEE Standard 485 recommends a design margin of 1.15 and an aging factor of 1.25 when sizing a new battery. Therefore, it is not obvious that battenes 2BD001 and 2DD001 have sufficient capacity.
PECO RESPONSE A new calculation has been prepared to evaluate the margin between the rated capacity of the batteries and the design load profile. This calculation uses the existing calculations as a basis for the design load profile and includes an allowance of 5% for uncertainty in the magnitude of individualioads presently not confirmed by field walkdown. The calculation evaluates the margin for both a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle. The results are as follows:
Percent Margin Percent Margin for 2 Hour for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Battery Duty Cycle Duty Cycle 2AD001 104 97 2BD001 52 8 2CD001 104 97 2DD001 52 8 This new calculation also evaluates the consequences of removing the starting resistors for various dc motor operated valve motors to resolve concerns related to NRC Information Notice 88-72. The increased inrush current has an impact on the battery load profile, reducing the available margin.
PECo has decided to adopt a design load profile of less than four hours, cor sistent with typical utility practice. Since the diesels start in approximately 10 seconds and restore power to the 480V auxiliaries including the battery chargers within 16 seconds after loss of offsite power,the batteries are only required to provide power for approximately 16 seconds. Thus,the typical utility practice of using a design load profile with a duration of two hours 3rovides a significant degree of margin.
The results of the margin calculations, witi the increased inrush current due to removing starting resistors in response to NRC Information Notice 88-72, are as follows:
1
7 --_ -
c Attachment 3 Percent Margin for 2 Hour
' Battery Duty Cycle 2AD001 104 2BD001 21 2CD001 104 2DD001 21 IEEE Standard 485-1983, which is applicable for sizing a new battery, recommends a design factor of 1.15 and an aging factor of 1.25, for a total margin of 44%.
However, IEEE Standard 450-1980, which is applicable for the ongoing assessment of available margin, implies in Section 6.6, " Service Test," that a battery is acceptable if it passes a service test which duplicates the design battery duty cycle, as this demonstrates that the battery meets the design requirements of the system.
A battery is acceptable for continued use when the design load profile changes, provided that a margin exists between the capacity of existing battery and that required to meet the revised load profile.
The battery discharge tests performed in 1987 demonstrated that the tested capacity of both batteries exceeded their rated capacity. Since battery capacity normally decreases only a few percent during the first 10 years of battery life, PECo concludes that the present battery capacity is still in excess of rated capacity.
Therefore, PECo concludes thatthe existing Unit 2 batteries are adequate for the restart of Peach Bottom Unit 2 without further analysis or testing. Due to the similarity of system design between Unit 2 and 3, confirmation of the adequacy of the Unit 3 battery is expected. Nonetheless, a similar evaluation of the Unit 3 -
batteries will be completed prior to the restart of Unit 3.
PECo is proceeding to prepare new base line calculations to define the loading profile for each Class 1E battery in Units 2 and 3. These calculations will be based on field walkdown data to establish the load from individual components and will be used for load management control to demonstrate that each battery is suitable for continued use in accordance with IEEE Standard 450. These calculations will be updated and formally revised on a regular basis to account for load changes as the result of plant modifications and plant operating procedure chanc es. Walkdown data is presently being collected, and preparation of these design aasis calculations for Unit 2 will be completed in 1989, and the calculations for Unit 3 will be completed in 1990.
2 ,
Attachmant 3
. TITLE: UNDERRATED FUSES PECO INTERPRETATION OF CONCERN _
NRC Information Notice 84-65 " Underrated fuses which may adversely affect operation of essential electrical equipment" was issued on August 6,1984. This notice identified the Gould-Shawmut TR-R100 fuses as having a~ dc voltage rating of lessthan 250 volts.
During the recent NRC Special ElectricalTeam inspection at the Peach Bottom Atomic Power Station Units 2 & 3, the following Gould -Shawmut TR-R100 fuses L . were identified in 250Vdc safety related applications:
1 Bus: 20D11-
. Circuit 29-1100'
_ RHR Pump Suction Cooling Valve MO-2-10-017 Bus: 30D011 -
Circuit 29-1100 -
RHR Pump Suction -
Cooling Valve MO-3-10-017
' PECO RESPONSE in response to the concern of TR-R100 fuses installed in safety related 250VDC applications, Non Conformance Reports (NCR's) P89050-216 and P89111-216 were generated to resolve this issue at PBAPS Units 2 & 3. These NCR's have been dispositioned to replace the TR-R100 Gould - Shawmut fuses with TR-5100 Gould - Shawmut fuses. The installation of the safety related TR-5100 fuse
. in MCC 20D11 (30D11) to replace the existing TR-R100 fuses will be completed prior to restart of each unit.
.The specifications for Gould - ShawmutTR-R and TR-5 fuses are described below:
Model TR-R TR-5 Ampere rating 100a 100a RK5 RK5~
Class Sym. Short Circuit Rating 200 KAIC 200 KAIC UL Listed No Yes DC Voltage Rating (Per UL 198L) 200VDC 600VDC The application of the TR-5100 fuse will provide a 600VDC rating while maintaining coordination with the upstream protective device. Calculation EE-7 Section E6 has l been revised to document circuit coordination with the new TR-5100 fuse.
1
(:( ". < 4, Attachment 3 l
'l L:
? A design review of the 125/250VDC power system was performed that concludedi '
the ratings of the remaining fuses are appropriate for the design application. A
- walkdown of the subject fuses has confirmed that the installed fuses match the
. design drawings. ;
- j. An engineering memorandum will be issued to electrical engineering and design :.
. personnel to clarify the significance of AC and DC voltage ratings of DC )
components. Special consideration for voltage the rating of fuses will be 1 highlighted. This memo will.be issued prior to restart of Unit 2.
h 2 !
Attachm:nt 4 TITLE: WRONG TYPE OF FUSES PECO INTERPRETATION OF CONCERN A. The dc control fuses installed in 250 Vdc MCC 20D11 compartment 29-1112 and 29-1121 are 10A while other MCC compartments have 6A fuses in their j control circuits. The adequacy of this situation needs to be evaluated.
B.1 Drawings E-26 and E-27 identify the fuses in fuse box 20D19 and 30D19 as Bussman Class RK5 type FRN,250 Vac. The installed fuses are Gould l
Shawmut Class RKS, type TR-R 250 Vac. The adequacy of the Gould Shawmut fuses needs to be evaluated.
B.2 Circuits 29-BD30604 and 29-BD30605 have 30A type "NON" and "KON" fuses installed while drawing E-26 indicates a type "FRN" fuse should be used. This discrepancy needs to be evaluated.
PECO RESPONSE A. Inconsistency of Control Fuse Sizes in 250 Vdc MCC:
The primary purpose of a control fuse is to provide short circuit protection.
Control fuses are sized such that the interrupting rating is not less than the maximum short circuit current of the control circuit. Although different from the other control circuit fuses in the MCC 20D11, the existing 10A fuses for compartments 29-1112 and 29-1121 provide adequate short circuit protection.
To provide consistency of control circuit protection inside the Unit 2 MCC's, the 10A fuses will be changed to 6A fast acting Bussman Limitron type fuses.
This work will be accomplished prior to restart of Unit 2. Any corresponding changes required in the Unit 3 MCC will be accomplished prior to restart of that unit.
B. Installed fuse type inconsistent with design documents:
- 1. An engineering evaluation indicated the time-current characteristics of the Gould-Shawmut TR-R fuse was similar to the Bussman FRN and resulted in no change to the electrical coordination.
Non Conformance Report (NCR) P899025-312 was initiated and I
dispositioned to reflect the installed Gould-Shawmut TR-R fuses on single line drawings, E-26, sheet 1, and E-27, sheet 1. Calculation EE-7, l Section E6 was also updated to reflect the time-current characteristics for the type TR-R fuses. This discrepancy was identified and documented by PECo prior to the NRC Special Electrical Team inspection. The related documentation has been revised and issued.
- 2. An engineering evaluation was performed and showed that the installed 30A "NON" and "KON" fuses provide electrical system coordination with the 200A type FRN supply fuse in 125 Vdc panel 2BD306. However,to provide consistency with the design documents, the "NON" and "KON" fuses are being replaced with "FRN" type fuses 1
o - - - - _ _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _
-'-~
Attachment 4.
~
as shown on drawing E-26, Sheet 1. This replacement will be completed prior to restart of PB APS Unit 2.
A walkdown of the Unit 2125/250 Vdc system has confirmed that no l :-
' additional discrepancies exist between the single line drawings and the
' installed fuses. A similar walkdown for Unit 3 will be done pnor to restart of Unit 3. Any identiited Unit 3 fuse discrepancies will be resolved prior to l_
!- Unit 3 restart.
S i
2 u____=:____-
p .
Attachment 5 f
l
}
i
-TITLE: LACK OF SURVEILLANCE PECO INTERPRETATION OF CONCERN The PBAPS 125V battery charger maintenance procedure M-57.4 does not include maintenance for the AC and DC breakers internal to the battery charger. Is this exclusion of breakers from Preventative Maintenance (PM) consistent with the PBAPS commitment and program for Preventative Maintenance for equipment and components or, is it an oversight where a vendor recommended maintenance has not been included in the plant PM procedure?
If the exclusion of the breakers from the plant PM is an oversight,is this an isolated deviation from the program or a result of programmatic weakness thatwould cause recurrence of a similar nature if not corrected?
Relay 27FF in the Diesel Generator System was not included in the yearly PM or Surveillance Testing. Is this calibration required to ensure operability or per vendor recommendation and thus not included in PM or ST by an oversight?. lf it is an oversight,is it an isolated case, or the result of a weakness in the PM program that may cause a recurrence of a similar nature?
PECO RESPONSE ~
The surveillance activity of safety related components such as the breakers and relays is based on vendor recommendations given in Technical Manuals and EQ documentation.
To assure adequate surveillance is being maintained a detailed review of the present PECo position on Equipment Surveillance, Generic Letter 83-28 actions, and other identified concerns was performed. The results of the review are summarized below:
- 1) Aspects of Generic Letter 83-28 addressing utility actions on vendor information for safety-related components have been fully responded to by PECo.
- 2) PECo commitments of Preventative Maintenance and Surveillance in areas identified in NRC Inspection Report 86-25 have been fulfilled. The Diesel Generator Room Supply Fans and Battery Room Exhaust Fans have been included in the Preventative Maintenance Program.
- 3) The Vendor Manual Update Program was completed in 1988, including the i revision of affected procedures.
- 4) PBAPS has a committment to the Commonwealth of Pa.to have a program defined for review, approval, and control of vendor manuals prior to restart of Unit 2.
- 5) Vendor manuals reviewed during the preparation of this response were found '
controlled and up-to-date.
1
Attachment '5 L
- 6) . Breaker and relay maintenance was included in the Plant Program where .
' required by the vendor.
l 'The AC and DC breakers identified during the inspection are installed in each battery charger. The basic function of the circuit breakers is to serve as a disconnect switch to isolate the battery charger from the AC and DC systems. The breakers are not used as protective devices either for thermal overload or short circuit current.
The circuit breakers as designed are adequate to achieve their functions in the -
battery charger without routine calibration. Exercising the breakers during maintenance of the battery charger is sufficient to provide assurance of their intended function. The confirmation of equ,ipmentisolation will be included in the PM program for each the battery charger pnor to Unit 2 restart.
Relay 27FF is a loss of field flashing voltage alarm relay, provided for each diesel generator. Relay 27FF has been provided to detect a loss of the 125Vdc supply voltage to the exciter and to annunciate the loss of voltage after a 20 second time delay. Improper relay operation will not prevent the diesel generators from starting or performing their safety function. The 27FF relays will be added to the PM program associated with each diesel generator and will be functionally tested prior to Unit 2 restart.
2
l
,; , t a"
' Attachment 6 L
L TITLE: QUESTIONABLE 13.8 KV SWITCHGEAR INTERRUPTING CAPACITY PECO INTERPRETATION OF CONCERN The NRC reviewed the PBAPS Calculation EE-7, Subsection E2 "AC System Fault Calculation" and raised a concern regarding the low margin in the 13.8kv circuit
- breaker interrupting duty. The margin was 1.3% as shown in the calculation.
The NRC also questioned the limiting case electrical distribution bus configuration assumed in the subject calculation. This case assumed "the recirc pump M-G set tripped, the auxiliary buses fast transferred to one offsite power source, and cooling towers D & E tripped". The NRC requested comparison of this case with the plant startup configuration of two recirculation pump M-G sets running on two offsite power sources before transferring to the one auxiliary system. It was pointed out to the NRC that the subject calculation is conservative as it did not include factors such as cable impedance. The NRC requested an evaluation of the conservatism in the
_' calculation .
PECO RESPONSE
" AC System Fault Calculation" was prepared for the Appendix R Breaker / Relay Coordination Study in 1986. The 1.3% margin of 13.8kv breaker interrupting capacity is based on ANSI standard C37.0101979.
The calculation has been revised to include the operating configuration case of two' recirculation pump M-G sets running on offsite sources. The margin obtained is 11.2% as compared with 1.3%. This confirms that the existing selection of the worst case operating condition was correct.
The calculation has also been updated to quantify the conservatism resulting from exclusion of the 13.8kv cable impedance. Accounting for cable impedance, the margin increases from 1.3% to 13.4%.
Therefore,it is concluded that the PBAPS Units 2 & 3 electrical system has adequate short circuit withstanding capability, as proven by the updated calculations.
1
Attachment 7 TITLE: ADEOUACY OF MCC FEEDER CABLE AMPACITY VERSUS BREAKER SETTINGS l
j PECO INTERPRETATION OF CONCERN Calculation EE-7, Subsection E-3, Page 5, notes that the long time delay settings of certain breakers feeding the MCC's exceed the ampacity of the feeder cables. As a 4 result, the possibility exists that without protective action, these cables may become l overloaded, and therefore overheated.
Calculation EE-7, Subsection E-3, documents breaker coordination. However,it does i not document the MCC feeder cable ampacities exactly, nor does it document the design load on the MCC feeders. The determination of the adequacy of the breaker settings for equipment and cable protection requires additional documentation.
PECO RESPONSE PECo has maintained the design philosophy that breakers feeding MCC's should be setto avoid the possibilty of inadvertent tripping. PECo considers the continued operation of Class 1E systems is more critical than preventing minor short duration cable overloading.
Feeder cables to individual loads require overcurrent protection,in addition to fault protection, since a com aonent failure or individual fault could result in over%ading of these dedicated feec er cables. However, cables to MCC's are not subject to the same type of overloads as the feeders to individual loads. The MCC feeder cables require short circuit protection, but the overload protection is controlled by the design process which limits the amount of load applied, rather than from breaker overcurrent arotection settings. Therefore,the long time element of the MCC feeder breaiersis not essential for cable overload protection. However,the continued operation of the MCC is essential for plant safety in the event of a design basis accident. Therefore, it is more prudent to set the long time delay element at a relatively high level to avoid the possibility of inadvertent tripping.
The cables feeding each MCC are sized on the basis of the anticipated running load for the MCC. In response to the NRC Special Electrical Team Inspection concern, a reevaluation has been performed which confirms that the feeder cable ampacity exceeds 125% of the anticipated worst case running load on the MCC. Therefore, there is no need to increase the size of any of the feeder cables.
PECo therefore concludes that the design, as it stands, is adequate and imposes no constraint on the restart of either Unit 2 or Unit 3.
PECo will revise calculation EE-7, Subsection E-3, to document the design philosophy for MCC feeder long time cable protection and to confirm the adequacy of the cable ampacity for the anticipated coincidental loading.
PECo will review the feasibility and cost benefit of providing an improved design for MCC feeder cable overcurrent protection. The review will be completed during the next refuel cycle following restart of Unit 2 and 3.
1
Attachment 8 4
i TITLE: DIESEL GENERATOR LOAD ANALYSIS PECO INTERPRETATION OF CONCERN The NRC Special Electrical Inspection Team identified inconsistencies between the emergency diesel generator loading calculation and the information presented in the FSAR Table 8.5.2.
Based on these inconsistencies the adequacy of the diesel generator to supply power during a plant DB A and shutdown conditions was questioned. Specifically the following concerns were identified:
- 1. Appropriate conversion of horsepower to KW loading of major individualloads.
- 2. Determination of the worst case dieselloading based on the conditions described in the FSAR Table 8.5.2.
- 3. Confirmation that the diesel generators are capable of supplying the identified worst case load for the required period of operation.
PECO RESPONSE A review of the Diesel Generator and Emergency Bus Loading tables of the UFSAR show that the highest load occurs on DG El during the 10-60 minute time interval of the DG loading cycle.
j The total load on DG El during this time interval consists of two 4 kV loads (one RHR I
pump and one Core Spray pump) and two 480Vioad groups each of which is supplied by a 500 KVA load center transformer.
The RHR pump motor load has been conservatively calculated to be 1604 KW based on the motor rating of 2000 hp and a fullload efficiency of 93%. This is the value used for the RHR pump motor in the load tabulation of the Voltage Regulation Study, dated January 1989. This value is considered conservative, as demonstrated by the pump test curves. These curves indicate a pump runout condition of about 12,000 GPM rec uiring 1900 BHP, while the design rated f!nw of 10,000 GPM requires l 1,800 BHP whic1 equates to a 1,444 KW load at 93% efficiency.
The second 4 kV load on DG E1 is the core spray pump. The nameplate values of 600
' horsepower and 93% efficiency result in a 481 KW design load.
Loads at 480V and below have been reviewed against the loads used in the Voltage Regulation Study, the single line diagrams, and schematics to determine
! conservative load values.
Since the major loads have been calculated on the basis of rated horsepower and nameplate efficiency, the potential for inadvertent overloading has been avoided as described in Section 2 of Generic Letter 88-15, power factor misapplication.
l 1
l Attachment 8 The diesel generator is not operated for base load generation, and is only required
. for sustained operation following a LOOP /LOCA and prior to restoration of offsite power. Therefore the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> rating is applicable. ,
i'
. The total KW load, assuming conservative loadings as described above is 3,006 KW for DG E1. This load is within the 3,100 KW,200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> rating of the unit. It is therefore concluded that the diesel generators are adequately rated to support
)
DBA loading for Unit 2 and emergency shutdown of Unit 3.
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