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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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5- .. ,
PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.Cl. BOX 6699 PHILADELPHI A. PA.19101
- v. s. Bo y ca (21st 84i-4soo SR. VICE PRESIDENT NUCLE AR POWE R September 16, 1983 Docket Nos. 50-277 50-278 Mr. Darrell G. Eisenhut Divit2 ion of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Peach Bottom Atomic Power Station Alternative Shutdown Program, Exemption Requests, and Fire Protection Modifications Progress Report
Reference:
- 1) Letter from J. W. Gallagher to D. G. Eisenhut, dated February 25, 1983
- 2) Letter from J. S. Kemper to D. G. Eisenhut, dated March 24, 1983
- 3) Letter from V. S. Boyer to D. G. Eisenhut, dated May 27, 1983
- 4) Letter from V. S. Boyer to D. G. Eisenhut, dated July 22, 1983
Dear Mr. Eisenhut:
Philadelphia Electric Company, in Reference 1, proposed to submit Peach Bottom's Fire Protection Modification Progress Report every four months, starting in May, 1983. We requested in a second letter (Reference 2), pursuant to 10CFR50.12, an extension in the date for submittal of design descriptions of an Alternative Shutdown System and for filing exemption requests f or Suppression Systems and Structural Steel Protection to September 16, 1983. Philadelphia Electric Company, in Reference 3, pursuant to 10CFR50.12, requested an exemption for penetration seal material. Further, we provided in Reference 4 a description of areas requiring emergency lighting as a result of the al.ternative shutdown design. )k7 ChY p9d'#psT. lj]b
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t Mr. Darrell G . Eisenhut - Page 2 This letter will provide: (1) the Fire Protection Modification Progress Report (see Appendix 1); (2).the design description of our proposed Alternative Shutdown System (see enclosed report), which includes exemption requests for Suppressi on ' Systems ; ( 3) structural' steel calculation methodology
- and calculation results (see Appendix 2); (4) elaboration on the penetration seal program, to include HVAC damper modifications;
~
and ( 5) . a description of proposed emergency lighting.
I. Modification Progress Report Included in the Modification Progress Report are several additional modifications required as part of
- our review program to meet Appendix "R" criteria:
i:
A. Saf e Shutdown Separation - III .G.2 - Continued refinement of our saf e shutdown analysis has identified additional cable which must be rerouted or encapsulated.
B. Automatic Fire Detection - III .F - We have completed our re-analysis.of all plant areas to 4
verify that automatic fire detection is provided in those areas which contain. saf ety-related raceway. Eight zones have been ' identified 'which' contain safety-related' cable and conduit which are not provided with detection. Safe shutdown
. can be achieved following a fire in any of these eight fire zones. Corrective actions planned for these eight zones are as f ollows:
(1) The cables.in the following three zones will
- be encapsulated to provide a 3-hour fire barrier. No detection will be provided.
- ' Fire Zone 6* Stai rwell #24 Fire Zone 5-7 Stairwell #18 i
Fire Zone 12-15 Stairwell #23
!
- The 6 represents the old fire zone number i'
~
for Stairway #24. The 4 represents the newly defined fire area that includes Stairway #24.
Consequently, the new fire zone number is 4-6.
i i-a t
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Page 3 Mr..Darre'll G. Eisenhut
, (2) . Area smoke detection will be added in the following three zones:-
Fire Zone 6-22 Drywell Access Hatch Fire Zone 13-28 Drywell Access Hatch Fire Zone 11-65c Future spent resin area (3) Safety-related cable in the following zone will be rerouted through a zone which is provided with automatic fire detection.
Fire Zone 11-72B Fuel Pool Holding Pump Compartment-(4) Our re-evaluation identified one fire zone for which an exemption request appears to be j ustifi ed . The zone evaluation included a l
review of past survey data indicating expected transient combustibles; accessibility, both from a radiation and pedestrian traf fic standpoint; qualification
~ of barriers surrounding the area; and the E
combustible loading in adjacent fire zones.
Based on the results of our re-evaluation, t
we are requesting, pursuant to Section 50.12 of the Commission's Regulations , an exemption to the requirement of 10CFR50, Appendix R, Section III.F in Fire Zone 51-136, Emergency Cooling Tower Stairwell, for the following reasons:.
Safety-related cables in conduit are located in this stairwell. No other fixed combustibles are located in this fire zone.
Access to the stairwell is provided by a single outside staircase. Entrance to the staircase is controlled by a locked fence
. gate. Security personnel control the' keys to this-gate. The stairwell entrance is located up .a single flight of stairs .and is a controlled security access door (card reader).
The Emergency Cooling Tower is remote from the Power Block and pedestrian traffic is mi nimal . The area is not used for storage
< of materials. Due to the remoteness from the powerblock and the restrictions on entrance to the area, current administrative
. . - - . ~ . --, - ._
j Mr. Darrell'G. Eisenhut Page 4 i
- controls of combustibles will preclude the presence of a fire hazard and automatic fire detection is not' warranted.
i -C. - HVAC Damper Survey 4
As part of_our safe shutdown / alternative shutdown wall survey, many walls were identified which require upgrading of duct penetrations. An
' additional program is now in progress to provide the necessary corrective action for HVAC ducts
. penetrating saf e shutdown fire barriers. The
- . results of the survey are as follows
4
- 1) 100 existing duct penetrations through safe shutdown walls have no qualified dampers and will be upgraded with qualified dampers .
- 2) 23 dampers exist but qualification is being verified.
- 3) 38 ducts through safe shutdown walls have 3-hour qualified dampers.
- 4) 12 ducts are yet to be field surveyed.
! We expect this ef f ort , as well as corrective
' actions , to be completed by June 1, 1984. If any
[. dampers are qualified for less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, but meet. fire resistive ~ requirements commensurate with the hazard in the area, exemption requests i will be made in a letter to be submitted' by December 2, 1983.
l I
l D. Encapsulation Program f - As part of our encapsulation program, there are
' 17 HPCI cables that require encapsulation on Unit No. 3. These cables were placed on " hold" i, pending finalization of the conceptual design for i alternative shutdown. Since the HPCI system is
(; now considered the primary source of reactor inventory control for alternative shutdown, these l- cables have been released ' f rom a " hold" _
condition. These cables are now included in our encapsulation / reroute schedule with a deadline of the next Unit No._ 3 refueling outage. These 4
. . , . , _ _ . _ . , _ , _ . ~ - . . _ _ , , , _ _ _ . . . _ _ . _ . . _ _ _ . . . - . _ _ . . . -
Mr. Darrell G. Eisenhut Page 5 modifications will also be included in the next e
Modification Progress Report.
6 II. Alternative Shutdown Design Description - III.G.3
, The enclosed report on Alternative Shutdown includes detailed descriptions of the methods for bypassing the three critical areas of the plant- housing redundant saf e ' shutdown components; the main control room, cable spreading area , and remote shutdown panel area.
i- Included in this report are tables listing required modifications . as well as necessary operator actions .
Final operating procedures will not be written until practice exercises are performed by the designated 4
operators during simulated fire scenarios.
1 Determination of the timing required before initiating these actions, as well as that timing needed to
,- actually perform- these actions , is still needed.
Particular attention should be given to the exemption requests and their bases identified in Section 7 of the report . Philadelphia Electric Company, pursuant
- to~10CFR50.12, requests an exemption from the fire suppression syst'em provisions of Appendix R, Sections III .G . 2 and III .G . 3, for eight areas (three per unit and two common areas) as described in the report.
4 Additionally, an exemption involving the 3-hour barrier provision of III.G.2 is requested in Section 7 of the report for one area in each unit. As modifications identified in this submittal are approved by the NRC, the work items will be specifically identified _in our Modification Progress Report.
III. Structural Steel - Calculation Methodology and Results
- III.G.2 We have reviewed safe shutdown areas which contain i exposed structural steel- members and developed a calculation. methodology for analyzing the need for protective measures. In Appendix 2, we have included copies of our calculation methodology, assumptions and conservatisms, calculation results for each area revi ewed , and propos ed actions .
i 4
i 1
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Mr. Darrell G. Eisenhut Page 6 IV. (Penetration Seal Upgrade Program - III.M The penetration seal upgrade program continues. As of September 9, 1983, approximately 1900 penetration seals have been upgraded. The survey of safe shutdown barriere (378) to identify. penetrations requiring sealing is approximately 50% complete and 3300 penetrations requiring upgrading have been identified.
- Due to the Philadelphia Local Asbestos Workers strike, the available work force has fluctuated considerably.
Since August 1, 1983, the necessary work effort required and schedule restrictions warranted a force of at least 120 asbestos workers on double shif t.
However, 70-80 workers have ' been the maximum number we have been able to obtain f rom surrounding union halls.
The available work force is working two shifts, and as asbestos workers become available, every ef f ort is -
being made to immediately put them to work at Peach Bottom.
In' order to reduce the estimated number of penetration seals requiring upgrade, a vertical wall fire test was run on May 23, 1983. Two more tests are scheduled for the end of October (delayed due to the required curing time for concrete), one a vertical wall test with additional plant seal details, and one a -floor test.
Although the first vertical wall test indicated favorable results with respect to the Appendix R,
. III.M criteria, we agreed with'the NRC staf f reviewer to run a floor test of these same details. 'For the floor test, exact duplication of the detail and its orientation will be tested, thereby providing correlation data to the completed wall test..
We will include in our letter of December 2, 1983, a report on the results of these fire tests conducted at
> Gold Bond Building Products , Buffalo, New York, in cooperation with Factory Mutual Research. A final evaluation can then be made of the polyurethane material included in any seal details qualified by these tests and retained in plant seal configurations.
We are hopef ul' that successful completion of these tests will qualify additional- plant seals, either totally or with less labor intcnsive' modifications.
Every reasonable ef f ort is being made to meet the March 1,1984, seal installation deadline; 'however, i
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Mr. Darrell G. Eisenhut Page 7 the aforementioned problems with the labor force have seriously curtailed production. Should the work force remain at existing levels, we estimate by March 1, 1984, completion of approximately 5200 seals; 1600 .
seals shy of our present goal. If this projection remains accurate, we will shif t our emphasis toward completion of all Unit 3 seal upgrade requirements
- . since we expect Unit -
- 2 to be in a ref ueling outage in the Spring of 1984.
. V. Emer gency Lighting - III .J As a result of the alternative shutdown analysis, we j have identified 6 new areas / locations per unit that will require emergency lighting. We expect that in support of safe and - alternative shutdown procedures, emergency lighting will be added in the following areas:
! a) HPCI alternative control station - Reactor Bldgs.135 '
b) HPCI turbine areas j c) Torus' areas ,
, d) RHR valve motor control centers e) Isolation valve rooms f)- 2B RHR pump room (Unit 2 only)
- g) 3D RHR pump room (Unit 3 only) l h) -Access and egress routes thereto l
As the details of the Alternative Shutdown System i became finalized, the exact locations of the emergency lighting systems will be established.
In Reference 4, routes of access and egress between
! the _ power. block and the High Pressure Service Water
! Pump Structure and Diesel Generator Structure were identifi ed . There is presently no need to provide emergency lighting in the diesel generator rooms or -
access to, since the alternative shutdown diesel control panels will be located within the power block which is provided with emergency lighting.
For the High Presure Service Water Pump Structure access and egress, we plan to' store portable lanterns with at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery supply in the switchgear rooms. Since the Appendix "R" rule is not specific i
about fixed versus ' portable lighting, it is our 1
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Mr. Darrell G . Eisenhut Page 8 position that we are in compliance with this requirement and are not requesting an exemption for this case.
We are confident that this letter, along with its enclosures , documents continued actions responsive to the increased fire protection requirements necessary at Peach Bottom,
- and indicates Philadelphia Electric Company's commitment to continued saf e plant operation.
I should you have any questions or require additional inf ormation, please do not hesitate to contact us.
Very truly yours, Attachments cc: A. R. Blough, Site Inspector Peach Bottom d
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s Appendix I Page 1 of 10 September 16, 1983 PBAPS Fire Protection Mod Progress Report Revised to Account for Proposed Alternative Shutdown System (This Report Supersedes the May 27, 1983, Report)
Kcy: 2-EOO means'" Unit 2 - End of Next Refueling' Outage" N/A - Not Applicable Expected Mod Description Status Completion Dates Mod. No.
R5 route ZD201024K and Design 2-EOO 1029B &
ZD201027B then complete for 1029A encapsulate in Fire reroutes.
Zone 4C. Outage work.
Encapsulate 4 raceways- Encapsulation N/A 1029A ZB2MV010, ZB2L367,8 of these raceways ZB2M603 in Fire Zone 4B. no longer required.
(Safe shutdown To Be Determined achieved using ADS /CS.
Necessary raceways not yet defined.)
Encapsulate .2 raceways- Encapsulati on N/A 1029A ZA2P473, ZA2M350
~
of these raceways in Fire-Zone 4C. no longer-required.
(Safe shutdown To Be Determined achieved using.
ADS /CS.
Necessary raceways not yet defined.)
Rcroute ZD201024K in Design complete. 2-EOO 1029B Fire Zones 5E and SG. - Outage work.
On3 tray and 3 conduits Encapsulation N/A 1029A nacd to be encapsulated of these raceways in Fire Zone 12B. no longer required.
(Safe shutdown To Be Determined
- achieved using ADS /CS.
Necessary raceways not yet defined.)
e
6- :s ~
Appendix-I Page 2 of 10 September 16, 1983
. Expected Mod ~ Description Status Completion Dates Mod. No.
Fix ZA3Ol827A (reroute. Reroute- Completed 1029B
~in Fire Zone 12C). complete'.
Encapsulation not required.
Encapsulate 1/2 SSA Encapsulation N/A 1029A racewaysLin Fire of these raceways
. Zone : 12C . - no longer required .
(Safe shutdown To Be Determined
-achieved using ADS /CS.
Necessary raceways
-not yet defined.)
Encapsulate ZB30179A,- Encapsulation N/A 1029A B in Fire Zones 13D of' cable not and 13G. necessary due-
.tx) alternative shutdown system and exemption request for torus area.
Encapsulate-cables Encapsulati on N/A lO29A
.. ZB 201800C , D, ZB202785A, of these cables
'1788A,1B, 1789A, 1814 A no longer in' Fire Zones 60 and 63. - required.
(Safe _ shutdown To Be Determined achieved using
. ADS /CS.
! .Necessary raceways
, _ not yet defined.)
Encapsulate cables Encapsulation N/A lO29A i ZA301018B, C in Fire of these cables Zone 62.- no longer
- requi red .
(Safe shutdown To Be Determined achieved using ADS /CS.
Necessary raceways not yet defined.)
?
r l
c- o- 1 Appendix I Page 3 of 10 September 16, 1983 Expected
~ Mod Description - Status Completion Dates Mod . No .
Encapsulate cables- Encapsulation- N/A 1029A
~ ZB3Ol799T, ZB301800C, of these cables D and ZA3Ol827A in Fire
~
no longer
. Zones 65A,. B,' C and 72D.- required.
(Safe shutdown To Be Determined achieved using ADS /CS.
Necessary raceways not yet defined.)
Encapsulate three conduits Encapsulation N/A 1029A in Fire Zone 75. (ZA3M603, of= cables ZB3L367,8) no longer required.
(Safe shutdown achieved-using ADS /CS.
Necessary raceways not yet defined. )
Encapsulate several 4kV Field surveys 12/31/83 1029A
. power feeds in Fire complete.
Zones 78A, B, E and Design in Fire zone.ll4. progress.
iEncapsulate conduits Field surveys 12/31/83 1029A
- ZA2B1249'and.ZC2B1247 . complete.
in Fire Zone .78A. Design in-
, progress. Fire zone redefined.
' Encapsulate conduits. Field surveys 12/31/83 1029A 4 ZC3B137,.ZC3B150 and complete.
Junction Box J17 in Design in.
- Fire Zone 78A. progress. Fire zone redefined.
I
! : Encapsulate several 4kV . No longer. N/A 1029A conduits in. Fire Zone 82. necessary 'due to safe shutdown strategy' change.
Encapsulate 1 conduit- Field survey 12/31/83 lO29A ZA3D00111n Fire Zone 117. complete.
Design'in t progress.
l
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s Appandix I Page 4 of 10 September-16, 1983 Expected Mod Description Status Completion Dates Mod. No.
. Encapsulate ZB3D1802A, Field survey 12/31/83 1029A B and ZD3DD01E in complete.
~ Fire Zone 118. Design in progress.
Encapsulate ZB3DD01E Number of 12/31/83 1029A
, in Fire Zone 119. conduits reduced due to new Saf e shutdown strategy change.
Field survey complete.
Design in progress.
Ralocate battery chargers Outage work Outage work 1029C 3BD03 & 3DD03, then complete. completed. lO29A cncapsulate ZB3BD01E . Field survey 12/31/83
'in Fire Zone 120. in progress (non-outage) for encapsulation .
Encapsulate ZB3 Bill 4A Encapsulation - N/A 1029A cnd ZD3DD01E in' Fire of cables Zone 120. not required due to new safe shutdown strategy and field survey results.
-Encapsulate cable Field survey 12/31/83 1029A OG05H in Fire complete.
-Zone.147. Design in progress.
Fire zones changed due to field survey results.
Encapsulate OG03H Field survey ~ 12/31/83 1029A in Fire Zone- complete.
122. Design in progress.
Appendix I '
Paga 5 of 10 September 16, 1983 Expected Mod Description Status Completion Dates Mod. No.
Redesign 2A1706R - Outage Outage work 1029A cncapsulate OGO3H work complete. completed.
in Fire Zone 124. Only OG03H 12/31/83
-(now ZA0G03H) (non-outage) will be encapsulated.
Redesign 2A1603R - Outage work Outage work 1029D encapsulate ZB2BD01E in (redesign) completed. 1029A Fire Zone 125. complete. 12/31/83 Encapsulation of (non-outage) 2A1603R not necessary. Field survey complete and design in progress for encapsulation of ZB2BD01E.
Ralocate battery charger Design 2-EOO 1029C 2DD03, then complete. 1029A
-encapsulate related Outage work.
cables in Fire Field survey (Modification 2bne 126. in progrees involves outage for work to relocate encapsulation. battery charger .
The new outage schedule (Unit 2:
Spring '84) precludes encapsulation before the 12/31/83 expected completion date.)
Encapsulate ZB2BD01E, Encapsulation N/A 1029A ZBOB6143C and unnecessary due
, ZB2Bil22A in Fire Zone to new safe shutdown 126. strategy and field survey results.
Encapsulate Field survey 12/31/83 1029A
-ZA2A1505A in complete.
Fire Zone 127. Design in progress.
... .=
Appendix I Page 6 of 10 September 16,-1983 Expected Mod Description Status Completion Dates Mod. No.
Encapsulate ZB2D1802A,: . Field survey. 12/31/83 1029A B cnd ZB2BD01E in complete.
Fire Zone 128. Design in
. progress.
Encapsulate ZA2B1249, Field survey 2-EOO 1029A ZA2B143 and-ZC2B1247 complete.
in Fire- Zone 130. ' Design in (Due to the high level progress. of radiation during opera-tion in Fire Zone 130 and the lengths of the runs-of ZA2B1249 and ZCZB1247 (250 feet), this modification must be done during an outage.)
. Redesi gn Work Completed 1029D cables ZA160.3J, K, L, complete.
2A1706J, K, L-in Fire Zones 132, 133, 134 and 1135 as required.
Encapsulate ADS /CS Cable To Be Determined 1029A raceways in - requiring Fire Zone - encaps ulation 147. not yet defined
' Upgrade penetration seals Concentrating 3/1/84 1110 to required ratings as- on Unit 3
-proviously committed in- outage work. See cover letter.
. correspondence from J. W. Gallagher to D. G. Eisenhut, dated 10/14/81.
Change the settings on. Complete 3-Completed 2-1029G tthn"following 4kV in Unit 3. 2-EOO 3-1029H circuit. breakers: Awaiting Unit 2-152-1505, Unit 2
- 152-1705,--152-1806; outage.
Unit' 3-152-1505 ...-
Unit 2-design 152-1806. complete.
1
-Appendix I Page 7 of 10 September 16, 1983 Expected.
Mod Description Status Completion Dates Mod. No.
Change the' settings on ' Complete 3-Completed 3-1029H ths 480V load' center in Unit 3. 2-EOO 2-1029G
- circuit breakers: Awaiting Unit 2-10131... 1322; Unit 2 Unit-3-1212 ...-1114.- outage.
Design complete.
'R: place the .following Qualified First refueling 2-1029J, 480V motor. control center breakers outage or planned Common-tagnetic-only circuit not outage that lasts at IO29K,.
breakers with thermal . currently least 60 days, com- 3-1029L magnetic. circuit breakers: available. mencing after 6/1/84.
Unit 2-3671 . . . - 2 8 51 ; 'Oualification Breakers still not Common-4955, 5055,-6131,- process in qualified. Schedule
' Unit 3-3851 .. 6033. progress. change due to
- (Ao previously committed outage change caused Eto in correspondence f rom by Unit 2 forced outage.
S. L. Daltroff to D.'G.
'Eisenhut, dated January 12, 1983.)
Add new. ground overcurrent Design 2-EOO 1029M
.rolays1to the following complete.
4kV circuit' breakers: Relays Unit 152-1606 and ordered.
152-1709. Awai ti ng Unit 2 outage.
- Rsplace the existing Design 2-EOO 1029N
. ground overcurrent relays complete.
f or the following 4kV - Relays circuit breakers: ordered.
Unit-2; 152-1606 and' Awaiting 152-1704. Unit 2 outage.
Add' eigh't hour -battery Complete Complete except lO29R power supply capability. ( Alternative for resolution to the Emergency Lighting - shutdown of startup System in the following system design problems in
' locations : Main Control. will add 3 areas.
R:om,-Remote Shutdown additional P:nels,LCable Spreading ' areas.)
Room ' (selected locations ), .
- Four Emergency Switchgear-
' Rooms, HPSW Pump bays-and the fifth' bay in the DG
' Building.
.- . .- l Appsndix I Page 8 of 10 September 16, 1983 Expected Mod Description : Status Completion Dates Mod. No.
Provide a water curtain Complete Completed .1029U in the west. corridors of rsector building, elev.
135 ; ' Units 2 and 3.-
Icolate the corridor Complete Completed 1029s behind the emergency
.cwitchgear rooms.
Provide dikes for Complete Completed 1029T Emsrgency Load Centers on elevation 165, Units - 2 and 3.
Provide smoke detectors Complete Completed 1029W in Fire Zones 78A and
. 82 since the zones have a fixed.
combustible loading and no' existing smoke-dstection-system.
Provide smoke detectors Complete Completed lO29W in Fire Zones 70, 72E, 72F, and 74 since the zones have a-fixed co2bustible loading-and no existing smoke antection system.
iProvide line type heat Testing in 9/27/83; (within 2 1029W
-dctectors in cable tray progress. months after-receipt
-in Fire . Zone 108 since . Material of materials)
.ths area has a fixed available combustible loading and 7/27/83.
no existing fire datection system.
Provide smoke detectors Complete Completed 1029W in Fire-Zones 76 and'77 due to-the possibility ~
of ' transient ' combustibles in these zones .
_ _ _ ~ , . - . . _ . - . .. . . ~
Appendix I Page 9 of 10 September 16, 1983 Expected 4
Mod Description' Status Completion Dates Mod. No.
Rsroute co'duit n ZB2D785 Design in 2-EOO 1029B
^
outside of Fire Zones progress. (administrative-
- 78B and' 78W. Materials controls will be available, provided after July 1, 1983, until completed.)
Additional Modifications Identified af ter ' original Safe Shutdown Report submittal.
l Encapsulate ZA2A1506A Complete Completed 1029A in Fire Zone 131.
Encapculate raceways Field ;s urveys 12/31/83 1029A
.ZAZM165 -and ZA2M166 'in progress.
in the north half of 1
' Fire Zone 5H.
Encapsulate raceway Field surveys 12/31/83 1029A.
ZB3P315' in the south in progress.
half of the Fire Zone 13H.
' Encapsulate eleven Field surveys To Be Determined 1029A
. raceways in Fire in progress.
Zone 72A as part of
- alternative shutdown
, Raroute 301019B and Design in 12/31/83 1029B
. encapsulate ' new progress.
- raceway in Fire Zone'78A.
. Rsrout'e.201019B, F Design in ' 12/31/83 1029B and encapsulate new progress raceway in-- Fire Zonef5H.
Encapsulate - ZC2A1705 A Design in 12/31/83 1029B
-and encapsulate in progress.
n:w raceway in Fire:
Zone 12C.
t
FE.-
' Appendix I Page 10 of 10 September 16, 1983 f'
Expected Mod Description Status ' Completion Dates Mod. No.
l 1029B Raroute_ZB202074A, Design in To Be Determined and. encapsulate progress.
- nsw;-racenay in' (part of CS/ ADS) 4 Fire Zone 4C.
Reroute-ZAB5944A Design'in 2 months f rom 1029B 4
from Fire Zone' progress. material availability 72B.
Install a single' Unit 3 3 - Completed -1029W enoke detector in Complete.
. thn_drywell access 4
hatch areas of- Unit 2 2 - Before end both units, Fire Design of present outage.
Zones 22 and 28. complete.
Tha detectors are Construction I to -be tied into existing in progress.
- loops on 135' of the Rx Bldgs.
i Encapsulate ZD2P219 Field survey 12/31/83 1029A in Fire 7,one 6. .in progress
)
- Encapsulate ZA2LO75 Field survey 12/31/83 1029A
. in Fire Zone 7. in progress.
! Encapsulate ZD3 LOO 4 Field survey; 12/31/83 1029A inLFire Zoneal5. in progress.
I L ' Install a single Design in Within 2 months 1029W c=oke detector in progress. after receipt of Firei Zone 65C. materials._
Th3 detector '. is - to be -
~
[.l . tied into the existing.
loop on 91'-6" of the s l Radwaste' Bldg.
l l :
Install 100 3-hour _Approximately 6/1/84 1309 i rated fire dampers 1/3 of-the 100
- ' in HVAC ducts new dampers will be i - penetrating fire - ordered by 10/1/83.
barriers. Attempt Delivery time is
~
l -_to qualify 23~HVAC estimated to be
' with 2 existing 4 weeks. _ Desi gn 1 l/2 hour fire is 30% complete.
. danpers in series
. for their-I accoptability in
! cafe shutdown fira barriers.
I l.