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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 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 V.' S. BO Y E'R SR. VICE PRESIDENT NUCLE A R POWE R May 16, 1984 Docket Nos. 50-277 50-278 Mr. Darrell G. Eisenhut i' Division of Licensing U.S. Nuclear Regulatory Commission i Washington, D.C. 20555
SUBJECT:
Peach Bottom Atomic Power Station Fire Protection Modifications Progress Report
REFERENCES:
(1) Letter from J. W. Gallagher to i D. G. Eisenhut, dated February 25, 1983
! (2) Letter from V. S. Boyer to D. G. Eisenhut dated December 2, 1983
Dear Mr. Eisenhut:
l Philadelphia Electric Company, in the reference (1) letter, proposed to submit Peach Bottom's Fire Protection Modifications Progress Report every four months, starting in May, 1983. In the reference (2) letter, the Licensee discussed the
- final penetration seal test reports received from Factory Mutual L
Research.
This letter includes: (I) the Fourth Modifications Progress Report issued to you (Attachment 1); (II) a copy of each final Penetration Seal Test Report forwarded to us by Factory Mutual Research (Attachment 2); (III) an update on the penetration sealing program; (IV) a schedule exemption request for certain dampers in our HVAC damper upgrade program; (V)- a schedule commitment for alternative shutdown; and (VI) a discussion of our safe shutdown instrumentation program.
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8405220274 840516 PDR ADOCK 05000277 i F PDR %
1 i t i
1
- e IMr. Darrell G. Eisenhut May 16, 1984 Page 2 I. Modifications Progress Report (Attachment 1)
~
A comparison of the attached Modification Status Report and the previous Modification-Status Report, dated January.16i, 1984, reveals that. twelve (12) estimated commitment dates of March 15,-1984, as established in the reference (2) letter,
- have been changed. Six (6) were changed to "2-EOO" and six (6) were changed to "next system. outage of sufficient duration". These changes were forced by outage. requirements or design delays for cable encapsulation and rerouting work (as. indicated in the previous' Modification Status Report, dated January 16, 1984.) Most of the completion.date slippage involves only short lengths of conduit leading to and including terminal boxes.
-II. Factory Mutual Research Penetration Seal Test Reports JAttachment 2)
- 1. Wall Test - May 23, 1984
- 2. Wall Test - November 3,1983
- 3. Floor Test - November 4,1983 III. Penetration Seal _Uggrade Program - III.M A. No. 2, Unit Control Room' Floor Penetration Seals The Alternative Shutdown Proposal submitted tx) the Commission and approved in a Safety Evaluation Report dated January 26, 1984, uses a safe shutdown method
-bypassing the Control Room and Cable Spreading Room.
These rooms were previously separate fire areas. We have now combined these fire areas into one area with different zone identifications. Therefore, since we have redefined these fire areas as being common, we do not plan to upgrade the control room floor penetration seals based on the following:
- 1. The Cable Spreading Room is' protected by area smoke
. detection and an automatic carbon dioxide system.
- 2. The Control Room is continuously manned. Although approximately 335' existing seals have material of thicknesses which have not been tested to qualify.
! for a 3-hour fire rating, all these seals provide a
! gas-tight seal. :In addition, in many of these
! cases, some minimum depth of grout is included.
!- The limited fire resistance'of the existing floor l'
{
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Mr. Darroll G. Einsnhut May 16, 1984 Page 3
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penetration seals will allow time for operator action.
- 3. Safe Shutdown would be accomplished from the same L alternative shutdown panels, whether a fire caused i evacuation of the Control Room or cable damage in the Cable Spreading Room.
1
- 4. Removal of existing material, such as grout from.
inside conduit, could jeopardize the integrity of ,
! the cable. (Most of the material removed on Unit 3 was polyurethane foam which was not as severe a removal problem as grout).
4 I
B. No. 3 Unit, Seal Upgrade Schedule On June 1, 1984, we expect approximately 3492 of 3545 penetration seals to be completed. The projected 53 incomplete seals are located in 31 barriers in 23 different rcams and have the following restraints:
- 1. Penetrations containing 4kv and 13kv cable i ;'
-The voltage is sufficiently high to prevent a safe
- work environment while the unit is operating. The 4
cable in the unsealed penetrations cannot be de-
- energized while the unit is operating.
t l 2. Penetrations contain circuitry associated with
! safety-related equipment which if disturbed could
- interrupt plant operation. The equipment ;
associated with the circuitry in these penetrations i cannot be taken out of service without affecting i
plant operation.
- 3. Penetrations located in areas of extremely high radiation The upgrading of penetrations :Ln these areas while i .the unit is operating would crette a significant l ALARA concern for the individuals involved.
l Therefore, station. Health Physics personnel have prohibited work in these areas until the unit is.
not operating.
- 4. Penetrations associated with fire dampers as described in Section IV of this letter. The k
4 w --y g- y 'un
- - m - w. yy., p. t- .
9
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~ Mr. Darrell'G. Eisenhut Ma'y 16, 1984 Page 4 annular regions external to the HVAC ducts in question will be. sealed after the installation of the fire dampers.
The above uncompleted penetrations will be upgraded as soon as safe access to the penetrations is possible, j These penetrations will be sealed during outages of 1 sufficient duration to encompass the access, blocking
, and installation requirements. As fire dampers are j installed, the associated penetration seals will also be
- . completed.
i C. The balance of uncompleted seals on No. 2 Unit will be finished by the end of the refueling outage.
i IV. HVAC, Damper _ Program - III.M The procurement and installation program to install 3-hour.
'. qualified. dampers in ventilation ducts penetrating safe 1 shutdown fire barriers is continuing. 'As a result of
! resurveys of. existing ductwork and dampers the number of i dampers to be installed is now approximately 90; 24 in No.12 L Unit, 22 in No.'3 Unit, and 44 in. common systems. Sixty-l five have been purchased. Damper installation has been very
{ difficult. Several reasons for the damper installation difficulties are:
- 1. Unforeseen problems with contamination of ductwork has
- almost doubled installation time. Ductwork which
- serviced very low level radiation areas has become
! slightly contaminated over the years. Work in some of l these ducts now requires not only Anti-C clothing but
!. also the use of portable HEPA filter units and i enclosures around the work area.
- 2. The increase in damper installation time has
, necessitated reevaluation of. critical equipment HVAC
. outages'to verify that sufficient cooling is provided to assure continued equipment operation / availability. In some cases, portable ventilation equipment is necessary, f
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- n. . , - +
L
7 Mr. Darrell G. Eisenhut May 16, 1984 Page 5
- 3. Similarly, our evaluations have revealed that outages are required for several areas because we can not assure critical equipment availability during operation without ventilation to that equipment. Two unit outages are necessary in some common areas.
We expect 5 dampers to be installed by the end of this month and are proceeding as quickly as station operating conditions allow. We expect increased productivity as installers become more familiar with the specific damper installation practices required.
Therefore, we hereby request, pursuant to the requirements of 10CFR50.12 an exemption from our previously transmitted completion schedule of June 1, 1984. Our proposed schedule would be to complete No. 3 unit damper installations by September 15, 1984. No. 2 Unit and Common damper installations will be complete by the end of the ongoing No. 2 unit refueling outage.
Those Unit 3 and common dampers requiring an outage will be completed during outages of sufficient duration to allow access, blocking and installation.
V. Alternative Shutdown - III.L A number of alternative shutdown modifications have been defined for each unit as well as for common plant systems.
These modifications have not yet been itemized on the attached PBAPS Fire Protection Modification Progress Report because PECo is still awaiting the issuance by the NRC of a revised Safety Evaluation Report on the September, 1983, submittal. Unit 3 alternative shutdown modifications are scheduled to be completed by the end of the 1985 Unit 3 refueling outage. Unit 2 alternative shutdown modifications are scheduled to be completed by the end of 1986 Unit 2 refueling outage. The common plant systems (Diesel Generator Controls and Emergency Service Water System controls) will be completed on the 1986 Unit 2 refueling outage. Consequently, alternative shutdown capability will not be available on either unit until the conclusion of the 1986 Unit 2 refueling outage.
VI. Safe Shutdown - III.G The June 1982 submittal provided design criteria to protect instrumentation cables for the process parameters. When the
e- 1 l
. . l Mr. Darrell G. Eisenhut May 16, 1984 Page 6 decision was made to install an alternative shutdown system, the work on the instrumentation rerouting was deferred due to different readout locations required for alternative shutdown. The work has now been re-initiated to provide sufficient information at both the alternative control
' stations and in the Main Control Room to safely shutdown the plant. We are presently planning to. include the applicable process parameters as defined in Attachment 1 to Information Notice 84-09. For Peach Bottom, these process parameters are:
a) Reactor water level b) Reactor pressure c) Suppression pool water level d) Suppression pool temperature e) Containment pressure f) Condensate storate tank water level g) In addition, diagnostic instrumentation (i.e., pressure or flow) will indicate the status of the following systems in the control room:
- 1) Reactor' Core Isolation Coolant (RCIC)
- 2) High Pressure Coolant Injection (HPIC)
- 3) Core Spray (CS )
- 4) Residual Heat Removal (;RHR)
- 5) High Pressure Service Water (HPSW)
- 6) Emergency Service Water (ESW)
Diagnostic instrumentation will indicate the status of the HPCI, RHR, HPSW, and ESW at the alternative control facility. The diagnostic instrumentation will be available at the appropriate local control panel location whenever its respective system is required for safe shutdown.
The identification of system and process parameter cables and the location of those cables has been completed. To protect cables associated with the instrumentation necessary for safe shutdown, rerouting and/or encapsulation of a portion of these cables will be necessary. Modifications (MODS 1029E, 1352B&H, 1353B&H) have been initiated to identify exactly which cables will be rerouted or encapsulated and modify them as necessary. Status of rerouting and/or encapsulation of these cables will be provided in the next submittal of the Peach Bottom Fire Protection Modification Progress Report planned to be submitted by September 17, 1984.
(.
, - e, Mr.'.Darrell G. Eisenhut May 16, 1984 Page 7 If you have any questions, please do not hesitate to call.
Very truly yours,
/
/ 4 Attachments cc: A. R. Blough, Site Inspector i
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Attachment 1 Page 1 of 11 May, 1984 PBAPS Fire Protection Mod Progress _ Report Revised to Account for Proposed Alternative Shutdown System (Does not Include Alt. SD Mods)
(This Report Supersedes the January, 1984, Report)
Kay: 2-EOO means " Unit 2 - End of Next Refueling Outage" N/A - Not Applicable Expected Mod _ Description Status Completion Dates Mod. No.
R route ZD201024K and Design 2-EOO 1029B ZD201027B then complete for enccpsulate in Fire reroutes.
Zona 4-4C. Outage work.
No encapsulation necessary.
Encapsulate 4 raceways Raceways are now N/A in Fire Zone 4B. defined for ADS /CS and no encapsulation is necessary.
Encapsulate 3 Encapsulation 2-EOO 1029A racGways in Fire complete except ZonD 4-4C - ZA2D855 for a short ZA2M001, ZA2D417 section of ZA2M417 delayed due to design difficulties and short sections of ZA2M001 and ZA2D855 associated with Junction Boxes.
Encapulation of Junction Boxes is outage work due to blocking requirements.
R;rcute ZD2Q1024K in Design complete. 2-EOO 1029B Firo Zones 6-5E Outage work.
Cnd 6-5G.
On3 tray and 3 conduits Raceways are now N/A ne:d to be encapsulated defined for in Fire Zone 11-12B. ADS /CS and no encapsulation is necessary.
1
_A
Attachment 1 Page 2 of 11 May, 1984-
)
Expected Mod Description Status Completion _ Dates Mod.,No.
Fix ZA3Q1827A (reroute Complete Completed 1029B in Fire Zone ll-12C).
Encapsulate Complete Completed 1029A ,
ZB3M002 in Firo Zone .11-12C.
Encapsulate ZB301794A, Encapsulation N/A B in Fire Zones13-13D' of cable not end 13-13G. necessary due to alternative shutdown system and exemption request for torus area.
Encapsulate 7 cables Raceways are now N/A in Fire Zones defined for 11-60 and 11-63. ADS /CS and no: encapsulation is necessary.
Encapsulate cables Raceways are now. N/A ZA301018B, C in Fire defined for' ADS /CS'-
Zone 2-62, and no encapsulation is ne>:essary.
Encapsulate 4 cables Raceways are now N/A
'in Fire Zones defined for ADS /CS11-65A, B, C and and no-encapsulation 72D.. is necessary.
Encapsulate ZA2M417; Complete Completed 1029A ZB3D002-in Fire Zone 11-75.
Encapsulate several.4kV Conduits are. . N/A
-power' feeds in Fire' installed within Zonas 78A, B,.E and permanent plant ^
Fire zone 114. walls in this area.
No encapsulation is necessary.
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Attachment 1 Page 3 of 11 May, 1984 Expected.
. Mod Description Status Completion Dates Mod. No.
Encapsulateiconduits Encapsulation 2-EOO 1029A ZA2B1249,J_ZC2B1247 complete for end ZA2B143 in Fire ZA2B143. ZA2B1249 Zonn=50-78A and ZC2B1247 must
' be rerouted before encapsulation.-
This is outage. work.
' Encapsulate conduits Complete : Completed -1029A
- ZC3B137, ZC3B150 and
- _ Junction Box J17 in Fire Zone 50-78A.-
Encapsulation 1/2 SSA Complete except 2-E00 1029A raceways in Fire for short Zone.50-78B. sections associated with Junction Boxes. Encapsulation of - Junction
. Boxes is' outage work due'to blocking requirements.-
Encapsulate several 4kV No longer. N/A'-
' conduits in' Fire- necessary due Zone 50-82 to' safe shutdown
' strategy change.
Encapsulate 1 conduit: No longer N/A
'ZA3D001 in Fire- '
necessary due LZone 30-117. to' safe shutdown progress.-
Encapsulate.ZB3D1802A,._ Complete' CompletedL 1029A B~and ZD3DD01E in Fire' Zone 31-118.
Encapsulate ZD3DD01E. . Complete Completed -1029A.
Lin' Fire. Zone.32-119.'
lRalocat'e; battery chargers Complete Completed '1029C-13BD03 & 3DD03,'then ~
.1029h-l:encspsulate;ZB3BD01E j ':in' Fire Zone 132-120.-
h L.
, a y - -.. , .. , ~- . -. d ; - J ;- _ y ,, ., , . . . , . , +
- e. .
Attachment 1 Page 4 of 11 May, 1984 Expected Mod Description Status Completion Dates Mod. No.
Enc:psulate'ZB3Blll4A Encapsulation N/A and ZD3DD01E in Fire of cables Zone 33-120. not required due to new safe shutdown strategy and field survey results.
Encapsulate cable Encapsulation N/A OG05H in Fire no longer Zono 11-147. necessary due to safe shutdown strategy change.
Encapsulate OG03H Encapsulation 2-EOO 1029A and ZA2AG121B in in progress Fire Zone 35-122. fG7 ZA2AG121B.
Complete for OGO3H.
Redesign 2A1706R - Outage 2-EOO 1029A encapsulate OGO3H work complete. Outage work and ZA2AG121B. Encapsulation completed, in Fire Zone 37-124. in progress for ZA2AG121B.
Complete for OGO3H.
-Redesign 2A1603R - Complete Completed 1029D encapsulate ZB2BD01E in 1029A
' Fire Zone 32-125.
Rolocate battery _ charger Design '2-EOO 1029C
'2DD03,_then complete. 1029A encapsulate related Outage work.
cables in Fire Field survey Zone 39-126. in progress for encapsulation.
'_ Encapsulate ZB2BD01E, Encapsulation _ N/A-ZB0B6143C and- unnecessary due i ZB2B1122A in Fire Zone to new safe shutds rn
[ 39-126. strategy and field survey results.
l Encrp ulate Complete Completed. 10'29A ZA2A1505A in Firo Zone 40-127..
b
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- Attachment 1 Page 5 of 11 May, 1984
. . Expected
- Mod Description Status- Completion Dates Mod._No.
Encapsulate ZB2D1802A, l Complete' Completed 1029A
-B and ZB2BD01E-in Fire Zone 41-128.
l Encapsulate ZA2B1249, To be rerouted 2-EOO 1029A ZA2B143 and ZC2B1247 to allow encap-in Fire Zone 50-130. sulation. (Due to the high level of radiation during operation in Fire Zone 130 and the length of the runs of ZA2B1249 and ZC2B1247 (250 feet),
, this modification must be done during an outage.)
Redesign Complete Completed 1029D cables 2A1603J, K,L, 2A170 6J , K, L -
e in Fire Zones43-132, 44-133,45-134 and 46-135 as required.
Encapsulate ADS /CS Complete - Completed -1029A
, raceways in Firo Zone 11-147.
Upgrade penetration seals Approximately 6/1/84. 1110 to required ratings as 5500 seals are for Unit #3 previouslyfcommitted in complete of an except'for correspondence from. estimated outage seals.
J. W. Gallagher to- 7200 total.~55 2-E00.
L '
D. G. Eisenhut, seals will dated 10/14/81. remain'on. Unit
- #3 - (see body
i of letter).
Remainder'are No. 2. Unit to.lme complete
. by end of outage.
j'Changethesettingson Complete-
'3 C- ompleted: 2-1029G.
tha1following 4kV. '
in Unit 3.. ~2-EOO '3-1029H circuit breakers: Unit'2 designt Unit'2-152-1505,'~ -
complete.
1522 1705,L152-1806; Unit'32152-1505'....
j 152-1806. . _
i,-> , *. , , , + , ,. -a w,* +- r -r -w q
Attachment 1 Page 6 of 11 May, 1984 Expected Mod Description Status Completion Dates Mod. No.
Chnnge the settings on Complete 3-Completed 3-1029H ths 480V load center in Unit 3. 2-EOO 2-1029G circuit breakers:. Awaiting Unit 2-1013 . . 1322; Unit 2 Unit 3-1212 ... 1114. outage.
Design complete.
Rsplace the Collowing Qualifica- First refueling 2-1029J, 480V motor ntrol center tion of outage or planned Common-magnetic-only circuit motor control outage that lasts at 1029K, breakers with thermal centers which least 60 days, com- 3-1029L magnetic circuit breakers: house breakers mencing after 6/1/84.
Unit 2-3671 ... 2851; is complete. Breakers still not Common-4955, 5055, 6131, PECo is work- qualified.
Unit 3-3851 .. 6033. ing with (As previously. committed Westinghouse to in correspondence from in order S. L. Daltroff to D. G. to obtain Eissnhut, dated qualified January 12, 1983.) breakers.
Add new ground overcurrent Design 2-EOO 1029M relays to the following complete.
4kV circuit breakers: Relays Unit 2-152-1606 and available.
152-1709.
Replace the existing Design 2-EOO 1029N ground overcurrent relays complete, for-the following 4kV Relay circuit breakern: order being Unit 2; 152-1605 and expedited.
152-1704.
Add eight-hour battery Complete Completed 1029R powsr supply capability (Alternative to the Emergency Lighting shutdown System in the following system design locations: Main Control will add Room, Remote Shutdown additional Pcnols,. Cable Spreading _ areas.)
Room - (selected locations) ,
Four Emergency Switchgear Roons, HPSW Pump bays and th2 fifth bay in the DG Building.
Prcvide a water curtain Complete Completed 10290 in thm west corridors of rc:cter building, elev.
135;iUnits 2 and 3. j
.e .
Attachment 1 Page 7 of.ll May, 1984 Expected
. Mod Description Status Completion, Dates Mod. No.
System Automation Design in 2-EOO of Water Curtain progress 3 - September 1029U in the West 15, 1984 Corridors of-reactor-building.
Icolate the corridor Complet>. Completed 1029S behind the emergency
, switchgear rooms.
4 Provide dikes for Complete Completed 1029T Em3rgency Load Cantors on elevation 165, Units 2 and 3.
Provide smoke detectors Complete Completed 1029W in Fire Zones50-78A and 50-82 since the zonas have a fixed combustible loading and no existing smoke 4 detection system.
Provide smoke detectors Complete Completed 1029W in Fire Zones 2-70,11-72E, ll-72F, and 11-74 cince the zones have a fixed combustible loading and no existing smoka detection system.
Provide line type heat Complete Completed 1029W datectors'in cable tray in Fire Zone 29-108 since the crea has a fixed combustible loading and no existing fire detection system.
Provide smoke' detectors Complete Completed 1029W in Fire Zones 26-76 and 22-77 due-to the' possibility of transient combustibles in th;se zones.
R;rcute conduit ZB2D785 Design 2-EOO 1029B cutCide of Fire Zones . complete. . (administrative 50-78B.and 50-78W.. Outage controls will be work. provided after July 1, 1983, until completed)~
Attachment 1 Page 8 of 11 May, 1984 Expected Mod Description Status Completion _ Dates Mod. No.
'Encrpsulate ZA2A1506A Complete Completed 1029A in Fire Zone-50-131.
Encepculate raceways Encapsulation 2-E00 1029A ZA2M165 and ZA2M166 complete except in the north half of for short sections Fire Zone 6-5H. associated with junction boxes. Encapsu-lation of junction boxes is outage work due to blocking requirements.
Enctpsulate raceway Encapsulation Next system 1029A ZB3P315 in the south complete except outage of helf of the-Fire for a short sufficient Zono 13-13H. section associ- duration.
ated with a junction box.
Encapsulation of junction boxes is outage work due to blocking require-ments.
Raroute 201019B, F Design in 2-EOO 1029B cnd encapsulate new progress Zens 5-5H.
Encapsulate ZC2A1705A No longer N/A in Fire Zone 11-12C. necessary due to change in safe
. shutdown strategy.
R3 route ZB2Q2074A, Design 2-EOO 1029B cnd oncapsulate complete.
n:w raceway in (part of CS/ ADS)
Firo Zone 4-4C.
R2 route ZA2B5944A Design in' 2-EOO 1029B from Fire Zone progress.11-72B..
,In toll ^a single Complete' Completed 1029W-cmoka detector in tha drywell access h tch areas of both: units, Fire Z n30 6-22 and 13-28. _ _ _ _ _ _ _ . _ _ _ _ _ -
Attachment 1 Page 9 of 11 May, 1984 Expected Mod Description Status Completion Dates Mod. No.
Ths detectors are to be tied into existing loops on 135' of the Rx Bldgs.
Encapsulate ZD2P219 Complete Completed 1029A in Fire Zone 4-6.
Enccpsulate ZA2LO75 Complete' Completed 1029A in Fire Zone 5-7.
Encapsulate ZD3 LOO 4 Complete Completed 1029A in Fire Zone 12-15.
Install a single Complete Completed 1029W cmoke detector in Firo Zone ll-65C.
The detector is to be tied into the existing loop on 91'-6" of the R dwaste Bldg.
Inctall 90 3-hour 58 dampers 2-EOO 1309 ccted fire dampers received. 3 - September in HVAC ducts Design is 15, 1984 penetrating fire 80% complete, barriers.
Modifications Identified after the September 16, 1983, Alternative Shutdown Submittal Instcll battery charger Design 2-EOO dependent 1029B cro:c-tie feeds, complete, upon equipment Thore cross-tie feeds delivery, will be' encapsulated c3 rcquired.
Enctp:ulate ZA2M416 To be rerouted 2-EOO 1029A-in Fire Zone 6-5H. to avoid encap-sulation-requirements, design in progress. i
- - _ ___.. . __ .._m. . _ .
Attachment 1 Page 10 of 11 May, 1984 Expected
. Mod' Description Status Completion _ Dates Mod. No.
Encapsulate cable Cable location 2-EOO 1029A
, ZD2B3983A in Fire dependent on 1
Zono 38-125. battery charger 2DD03 relocation, !
requires an outage.
Enccpsulate ZB3M149 Encapsulation 2-EOO 1029A cnd ZD3D489 in Fire in progress for Zona 32-119. ZB3M149, ZB3D489 to be rerouted to avoid encap-sulation, design j in progress, s
Encapsulate ZB3M149 Encapsulation 2-EOO 1029A i in Fire Zone 33-120. in progress.
R31ocate B and D Design being 2-EOO 1029B Diesel Generator MCC investigated, fesdn as identified in tha body of the letter.
Thace feeds will be
- encapsulated as required.
Encapsulate ZC3D481 Encapsulation 2-EOO 1029A
, cnd ZC3D482 in Fire in progress.
Zono 34-121.
4 Encapsulate ZA2D841 Encapuslation 2-EOO 1029A in Fire Zone 35-122. in progress.
EncEpsulate ZC3D481 Encapsulation '2-EOO 1029A
. cnd ZC3D482 in Fire in progress.
Zono 36-123.
4
, Enccpsulate ZA2D841 Encapsulation 2-EOO 1029A in Fire Zone in progress..37-124.
Enctpsulate ZC2A484 Complete . Complete 1029A in Fire Zone 48-144.
R0 route 5 cables in . Design 2-EOO 1029B Firo Zone 6-SH - .
complete.
ZC2B3814A;~ZC201228A, Br ZC2Q1230B, C.
R0rcute 3C2Q1228B. Design 2-E00 1029B dnd'ZC2Q1230B in- complete Firo Zone ' 6-5J. :
L
, + . ,-
Attachment 1 Page 11 of 11 May, 1984 Expected Mod Description Status ' Completion Dates Mod. No.
R3 route 4 cables in Unit 2 2-EOO 1029B Firo Zone 25-72A - design 3 - Next system outage ZC2Q1221B; ZC2Q1230B complete. of sufficient ZD3Q1227B; ZD3Q1229B Unit 3 duration.
complete except for circuit switchover.
Raroute 5 cables in Complete 3 - Next system 1029B Firo Zone 6-13H except for outage of sufficient ZD3B3952A; ZD3Q1227A, B; circuit duration ZD3Q1229B, C. switchover.
Raroute ZD3Q1227B Complete except 3 - Next system 1029B cnd ZD3Q1229B in Fire for circuit outage of Zona 6-13J switchover sufficent duration.
Roroute 12 cables in Unit 2 design 2-EOO 1029B Fire Zone 28-78H complete. Unit 3 - Next system (Cable Spreading Room) 3 complete outage of except for sufficient duration circuit switchover.
R3 route 6 cables in Unit 2 design 2-EOO- .1029B Firo Zone 29-108 complete. Unit 3 -Next system (Main Control Room) 3 complete outage-of except for sufficient duration.
circuit switchover.
Install 2 addi- Complete Completed 1029W tional smoke l d2tsctors in Fire Zcna 50-78A to provide area covorage.
1 1
1 b._s