|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000278/LER-1999-002, Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER1999-07-12012 July 1999 Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209D9781999-07-0808 July 1999 Forwards Addl Info to Support EA of Proposed 990212 License Application ECR 98-01675,correcting Minor Administrative Errors in TS Figure Showing Site & Exclusion Areas Boundaries & Two TS SRs ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20209E1131999-06-30030 June 1999 Forwards Proprietary NRC Form 398, Personal Qualification Statement-Licensee, for Renewal of RO Licenses for EP Angle,Md Lebrun,Jh Seitz & Zi Varga,Licenses OP-10646-1, OP-11081,OP-11082 & OP-11085,respectively.Encls Withheld ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209C1201999-06-30030 June 1999 Informs of Util Intent to Request Renewed License for PBAPS, Units 2 & 3,IAW 10CFR54.Licensee Anticipates That License Renewal Application Will Be Submitted in Second Half of 2001 05000277/LER-1999-004, Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities1999-06-20020 June 1999 Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities ML20196A5291999-06-14014 June 1999 Forwards Final Pbaps,Unit 3 TS Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal-hydraulic Stability Solution Hardware ML20195E6051999-05-27027 May 1999 Requests Exemption from Requirements of 10CFR72.44(d)(3) Re Submittal Date for Annual Rept of Principal Radionuclides Released to Environ.Exemption from 10CFR72.72(d) Re Storage of Spent Fuel Records,Additionally Requested ML20195B8171999-05-25025 May 1999 Forwards Final TS Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20195B6191999-05-19019 May 1999 Forwards PBAPS Units 2 & 3 Annual Radiological Environ Operating Rept 56 for 980101-1231, Per Section 6.9.2 of Ol. Trace Concentrations of Cs-137 Were Found in Sediment Consistent with Levels Observed in Previous Years ML20206P9171999-05-10010 May 1999 Updates Some of Transmitted Data Points Provided in Data Point Library ERDS for Pbaps,Units 2 & 3.Data Point Info Format Consistent with Guidance Specified in NUREG-1394 ML20206K6581999-05-0404 May 1999 Forwards PBAPS Bases Changes Through Unit 2 Bases Rev 25 & Units 3 Bases Rev 25.Bases Reflect Change Through Apr 1999, Thereby Satisfying Frequency Requirements of 10CFR50.71 ML20206D4651999-04-29029 April 1999 Forwards Rev 16 to UFSAR & Rev 11 to Fire Protection Program (Fpp), for Pbaps,Units 2 & 3.Page Replacement Instructions for Incorporating Rev 16 to UFSAR & Rev 11 to Fpp,Encl ML20207B8431999-04-23023 April 1999 Forwards Final Rept for 981117,plume Exposure Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific for Peach Bottom Atomic Power Station.One Deficiency & 27 Areas Requiring C/A Identified ML20206C5461999-04-20020 April 1999 Forwards Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2. Revs Made to ODCM & Station Process Control Program (PCP) During Rept Period,Encl 05000277/LER-1999-003, Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding1999-04-16016 April 1999 Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv)1999-04-0808 April 1999 Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities ML20205J0831999-03-26026 March 1999 Requests Enforcement Discretion from Requirements of PBAPS, Units 2 & 3 Ts.Enforcement Discretion Pursued to Avoid Unneccessary Plant Transient Which Would Result from Compliance with TS ML20205B6421999-03-24024 March 1999 Submits 1998 Annual Decommission Rept for Pbaps,Unit 1. There Were No Reportable Events Involving Unit 1 for 1998 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7171990-09-18018 September 1990 Comments on SALP Board Repts 50-277/89-99 & 50-278/89-99. Author Pledges Continued Mgt Support of & Attention to Rate of Improvement,Achievement of Goals & Performance of Routine Activities ML20065D4421990-09-14014 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Proposed Schedules for Operator Licensing Exams, Requalification Exams & Generic Fundamental Exams Encl ML20064A7751990-09-13013 September 1990 Advises That Ba Stambauth No Longer Maintains Need to Hold Senior Operator License ML20065D3741990-09-11011 September 1990 Forwards Rev to Relief Request 10-VRR-2 Re RHR stay-fill Supply Check Valves,Per ML20059F0541990-08-31031 August 1990 Responds to NRC Re Violations Noted in Safety Insp Repts 50-277/90-13 & 50-278/90-13.Corrective Actions: Training Will Be Provided for Personnel Re Requirements of Drawing E1317 & Administrative Procedures A-2 & A-6 ML20028G8181990-08-27027 August 1990 Forwards Peach Bottom Atomic Power Station Semiannual Effluent Release Rept,Jan-June 1990. No Revs Made to ODCM During Rept Period ML20059A6461990-08-15015 August 1990 Responds to Violation Noted in Insp Repts 50-277/90-200, 50-278/90-200,50-277/90-06 & 50-278/90-06 & Payment of Civil Penalty in Amount of $75,000.Corrective Actions:Emergency Svc Water Sys Restored to Operable Status ML20058N1991990-08-0909 August 1990 Advises of Change of Address for Correspondence Re Util Operations.All Incoming Correspondence Must Be Directed to One of Listed Addresses ML20058Q4051990-08-0606 August 1990 Forwards Public Version of Revised Emergency Response Procedures,Including Rev 12 to ERP-140,App 2,Rev 13 to ERP-140,App 3,Rev 4 to ERP-230,Rev 3 to ERP-305 & Rev 3 to ERP-660 ML20058M6631990-08-0303 August 1990 Responds to NRC 890406 Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81.Based on Encl Schedule,Overall Projected Implementation Date Will Be 901119 ML20056A9611990-08-0303 August 1990 Notifies That Be Saxman Terminated Employment & Operating Responsibilities W/Util on 900706 ML20081E1581990-07-30030 July 1990 Forwards List of 1990 QA Program Changes for Plant.List Identifies Page & Paragraph Number,Brief Description & Type of Change ML20056A0421990-07-27027 July 1990 Forwards Updated Human Resource Status Rept for Jan-Jul 1990 for Areas Identified in Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81 ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML20055H8331990-07-20020 July 1990 Submits Change of Addresses for Correspondence Re Util Nuclear Operations ML20044B2621990-07-12012 July 1990 Forwards Annual Progress Rept on Implementation of Control Room Enhancements,Per NUREG-0737.Corrective Actions for All Priority 1 Human Engineering Discrepancies Completed for Unit.Remaining Priority 2 Discrepancies Under Reevaluation ML20055G5481990-07-11011 July 1990 Forwards Public Version of Revised Epips,Including Rev 12 to ERP-140,App 3 & Revs 3 to ERP-310 & ERP-317 ML20043H7041990-06-21021 June 1990 Forwards Endorsements 143-146 to Nelia Policy NF-140 & Endorsements 93-96 to Maelu Policy MF-67 ML20044A2961990-06-21021 June 1990 Submits Revised Response to NRC Bulletin 89-002 Re safety- Related Swing Check Valves to Be Installed on Emergency Diesel Generator.Bolts Will Not Be Replaced Because Valves W/Original Internal Bolts Meet Requirements of Bulletin ML20043H6081990-06-19019 June 1990 Corrects 900427 Response to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing - 10CFR55 & Conforming Amends. ML20055C7621990-06-18018 June 1990 Informs NRC of Plans Re Licensing of Senior Reactor Operators (Sros) Limited to Fuel Handling at Plants.Util in Process of Implementing New Program for Establishment & Maint of Licensed SROs Limited to Fuel Handling at Plants ML20043G8131990-06-13013 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-277/90-06 & 50-278/90-06.Corrective Actions:Surveillance Test 6.16, Motor Driven Fire Pump Operability Test, Will Be Revised ML20043H0111990-06-12012 June 1990 Advises That AR Wargo Reassigned from Operating Shift Responsibilities & Will Be Resigning License,Effective on 900514 ML20055D1141990-06-0808 June 1990 Forwards Public Version of Revs to Emergency Response Procedures,Including Rev 9 to ERP-140 & Rev 3 to ERP-315 ML20043D7351990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-277/90-04 & 50-278/90-04.Corrective Actions:Procedural Controls Strengthened to Preclude Licensed Operators from Performing Licensed Duties W/O Successfully Passing Exams ML20043E9261990-06-0404 June 1990 Forwards Response to 900327 Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043D2681990-05-31031 May 1990 Forwards Response to NRC Requests Re PECo-FMS-0006, Methods for Performing BWR Reload Safety Evaluations. Util Core Monitoring Activities Routinely Access Accuracy of steady-state Physics Models Used in Evaluation of Parameter ML20043D6451990-05-30030 May 1990 Responds to NRC 900503 Ltr Re Violations Noted in Insp Repts 50-277/90-08 & 50-278/90-08.Corrective Actions:Glaucoma Testing Program Initiated for Security Personnel & Necessary Equipment to Perform Glaucoma Testing Onsite Obtained ML20055C5491990-05-18018 May 1990 Forwards Response to Request for Addl Info on 900412 Tech Spec Change Request 89-20 Re Postponement of Next Snubber Visual Insp,Due 900526,until Scheduled mid-cycle Outage in Fourth Quarter 1990 ML20055C5121990-05-18018 May 1990 Provides Info Inadvertently Omitted in Re Property Insurance Coverage for Plants.Limerick Generating Station Unit 2 Should Have Been Ref as Being Included Under Insurance Coverage ML20055C4851990-05-15015 May 1990 Forwards Annual Financial Repts for 1989 for Philadelphia Electric Co,Pse&G,Atlantic Energy,Inc & Delmarva Power & Light Co ML20043A3341990-05-14014 May 1990 Advises of Util Proposal to Provide Response to NRC Request for Schedule for Compliance W/Reg Guide 1.97 Re Neutron Monitoring Instrumentation 3 Months After NRC Concurrence W/Bwr Owners Group Design Criteria ML20042E7651990-04-27027 April 1990 Informs That Mod 2285 Completed on Unit 3,but That Mod 2285 Will Not Be Completed on Unit 2 During 8th Refueling Outage ML20042E8931990-04-27027 April 1990 Responds to Violation Noted in Insp Rept 50-278/90-01. Corrective Actions:Automatic Depressurization Sys Logic Sys Functional Tests Will Be Revised to Include Guidance in Unique Application of Test Lights ML20042F3241990-04-27027 April 1990 Advises That Organizational Changes Made in Advance of Approval of Tech Spec Change Request 88-06.Changes Do Not Present Unreviewed Safety Question ML20042E8741990-04-27027 April 1990 Responds to Generic Ltr 87-07, Info Transmittal of Final Rulemaking for Revs to Operator Licensing. Certifies That Limerick Operator Requalification Training Program Renewed on 900125 & Peach Bottom Subj Program Renewed on 890622 ML20012F4801990-04-0202 April 1990 Forwards Errata to Unit Shutdowns and Power Reductions Monthly Operating Rept for Feb 1990 ML20012F0971990-03-22022 March 1990 Forwards Summary of ASME Repairs & Replacement Completed, Per Facility Second 10-yr Interval Inservice Insps Completed During 900331-891111 Extended Refueling Outage ML20012E2151990-03-20020 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' for Peach Bottom.Response for Limerick Generating Station Will Be Provided by 900504 ML20012C2931990-03-12012 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey, Per 900118 Request ML20012B6211990-03-0808 March 1990 Provides Actions Taken to Ensure & Verify Sys Design Basis Performance,Per 900205 SSFI at Facility ML20012B9011990-03-0606 March 1990 Forwards 870331-891111 Inservice Insp Program Final Rept for Peach Bottom Atomic Power Station Unit 3 1987-1989 Extended Refuel Outage. Several Indications Identified ML20012A2661990-02-26026 February 1990 Forwards Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Tech Spec Change Requests 89-13 & 89-14, Revising Nuclear Review Board Membership & Meeting Frequency & Adding Independent Safety Engineering Group Requirements ML20011F2541990-02-23023 February 1990 Forwards Revs to Physical Security Plan.Encls Withheld (Ref 10CFR73.21 & 2.790) ML20011F3791990-02-21021 February 1990 Provides Revised Schedule for Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 & Explanation Why Jan 1993 Completion Date Cannot Be Met Due to Unavailability of Matls.Intallation Scheduled for Cycle 9 Outage ML20006F5491990-02-16016 February 1990 Certifies That 891122 Tech Spec Change Request (Tscr) 89-15, 891228 Tscr 88-18 & 900214 Tscr 90-04 Mailed to Commonwealth of Pa,Dept of Environ Resources ML20006F1621990-02-15015 February 1990 Forwards Progress Rept Re Implementation of Control Room Enhancements as of End of Seventh Refueling Outage,Per NUREG-0737.Rept Delayed to Allow for Independent Verification of Control Room Enhancement Status ML20012B1731990-02-15015 February 1990 Forwards Public Version of Revs to Epips,Including Rev 5 to ERP-101,App 1 to Rev 13 to ERP-110,App 2 to Rev 10 to ERP-110,App 1 to Rev 7 to ERP-140,App 2 to Rev 10 to ERP-140,App 3 to Rev 11 to ERP-140 1990-09-18
[Table view] |
Text
___________ _ ____ -
. -o PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA 19101 tats) eat sooi
- oseni w. cattroncn October 5, 1988
,2 3 : %'::,% .
Docket Nos. 50-277 50-278 Mr. W. R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Peach Bottom Atomic Power Statio.
Appendix R Pire Protection Modification
Reference:
Letter from J. W. Gallagher (PECo),
to W. R. Butler (NRC), dated October 16, 1987
Dear Mr. Butler:
My letter of October 16, 1987 forwarded safety evaluations to you to satisfy a request made during the July 30, 1987 meeting at Peach Bottom with your staff relative to fire protection modifications.
I The design of modification 2285 has since been completed and its safety evaluation is enclosed in order to fully satisfy the request of your staff. i The modification will assure minimum flow protection for the RHR postulated Appendix R fire.
pumps which are required to operate during a This modification will be implemented on Unit 3 during the current ploe replacement outage and on Unit 2 during the next refueling outage. As discussed in the July 30, 1987 meeting, temporary modification 2084 has been implemented on Unit 2 and assures conformance with the Appendix R requirements on Unit 2 until Modification 2285 is implemented.
0810130337 091005 00 PDR ADOCK05000{7 ff 9F 1
Mh. W. R. Butler, Director October 5, 1988 Page 2 If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, Attachment cc: Addressee 1 White Plint North 11555 Rockville Pike Rockville, MD 20852 W. T. Russell, Administrator, Region 1, USNRC T. P. Johnson, USNRC Senior Resident Inspector T. E. Magette, State of Maryland J. Urban, Delmarva Power J. T. Boettger, Public Service Electric & Gas H. C. Schwemm, Atlantic Electric l
i l
l l
l l
l 1
l l
- 4 # ' NUCLUR Err.!NEEF lts' ATTACHMENT
~ .
N2-1, 2301 Market Stree Safetv Evaluation for Mod 2285, Rev. O Peach Bottom APS Unit 3 Flie: Safety 2 (Mod 2285)
Doctype 565 I
SUBJECT:
This rrodification provides mlnitrun flov protection to PHR Pu o 3AP35 in the event of an Appendix R fire in Fire Area 13 North by Installing an alternate power supply to RHR Minlrun Flov Bypass Valve MO 3-10-16A. i 11 CONCLUS!Or t:
This rrodification affects safety-related coulpnent. It does
] involve an unreviewed safety cuestion. A change to the Techn!-
not a
This rrodification does in-cal volve Specifications safe shutdown is equipment, not required.however safe shutdown capability f
i in the event of a fire Is maintained. Neither a license amendment A sIgnifIcant hr.:a rds nor prior NRC approval Is required.
consideration is not involved, i l
!!! DISCUSSION: t As a result of the analysis of ssfe shutdown cacability in cor ollance with loCFR50, Appendix R, a rrodification to the power supply for RHR MinirnJm F1cw Bypass \'alve MO 3-10-16A is recuired.
This analysis shcvis that a fire In Fire Area 13 North (13N) could affect valve 0 era: Illty and ,eopard!:e mininum flow T"Ote: kn for- RHR Pep 3Ac35. )
i An Appendix R fire in Fire Area 13N reculres RHR Puro 3AP35 for suporession pool cooling, a0 proximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into the fire scenaric, to r-alntain suppression pool temperature within RHR Pump NPSH limits. Normally, when the puro is running without a suf-ficient ciscnarge path, MO 3-10-16A opens on a high differential pressure slgnc1 to prevent puno damage. Load Center 30810, which feeds MO 3-10-16A via ICC 30536, is located in Fire Area 13N and could beccme de-energt:ed during an Aopendly R fire in this fire area. Minimun flov protection for Pump 3AP35 is lost when the puro starts autcrratically on valid signals with no power available to MD 3-10-16A. There r ay not be enough tire for an operator to i
recognl:e the situation and trip the pu o.
't This redlfication relocates MD 3-10-16A trotor control eculo-I ment from 400V MCC 30E36 to an auxiliary motor controller. Pover to the auxillary retor controller will be supplied fecm a kBOV autcr-a-l tic transfer swltch. Non-21 paver to the switch will be supolled from the present pcwer supply, MCC 30936 (Safeguard Chan-nel ZA). Tne auto-transfer sultch will operate on a several second tire delay after normal power is lost. Unit 2 MCC 20836,
- - , , - . . - - -~-j-,-,.,--m- , . - -
,-4,,--.m.-y_m, -
., ,- - , , -. &,_,_~y---.m--_ ,-ume ,p. c ..y.-. - .,e.- -y- - - . -.
which is e iallable during a fire in Fire Area 13N, will serve as the backup power supply to the switch. The time delay will prevent the auto-transfer switch f rom operating during the loss of one offsite source and consecuential transfer of affected 4kV busses to the other off-site source. !
The auto-transfer swltch will be located in the E13 Emergency '
Auxiliary Switchgear Rocm. The aux 111ary r:utor controller will be located in the Unit 3 Rect re M-G Set Rocm. Both are safety-related and envirorynentally and seismically cuallfled as required.
The automatic transfer is accorrolished by a rnechanically-Interlocked, solenold-operated double throv switch. or This ensures backup.
only one of two possible switch positions - nonnal There is no off position. The auxillary trotor controller contains a manual bypass switch to permit bypassing the auto-transfer switch for testing purposes. In the normal position, the aux 111ary retor In the bypass controller is f ed f rom the auto-transfer switch.
position, the auxillary notor controller is fed directly f rom MCC 30836.
Existing control room valve controls, position Indication and i trotor thermal overload ennunciation are not changed by this rodification.
Additional control room annunciators are provided to alarm when the auto-transfer swltch operates, the auxillary retor controller door 15 opened or the manual bypass switch is in the bypass position.
There Is no significant net increase in load on the plant ,
electrical system as a result of this modification. Unit 2 MCC 20B36 has sufficient capacity to power ft 3-10-16A If recuired.
Electrical ! sol tion via circu't breakers is provided betweer. W normal and backup power sources and the auto-transfer switch.
The design of this modification meets the Intent of Standby Regulatory Gulde 1.6, "Independence Between Redundant Pover Sources and Between Their Olstribution Systems," and IEEE 308-1978, "IEEE Standard Criterla for Class IE Pover Syster.s for Nuclear Pover Generating Stations." Reg. Guide 1.6 and IEEE 308-1978 do not permit automatic transferring of loads between redundant standby Class 1E poner sources. For this modification, the norrral and backup pover supplies to the auto-transfer switch are not redundant since they originate frcm the same emergency diesel-generator.
During the normal and design basis accident operation of RHR d Ptmp 3AP35, MD 3-10-16A is ocwered frem its norrral 480V source and will function as designed previous to irrelementation of this r-od i f i cat i on. The autcr atic transfer to the Unit 2 backup source occurs on a tlrne delay after normal pover is lost and on the condition that backup pcwer is evallable. The time delay prevents s an auto-transf er unless a sustelned 1 css of normal ocwer is sensed by the switch circultry. The auto-transfer switch resets auto-r-atically when nortral pover is restored.
In the event of a fire in Fire Area 13N, mininum ficw protec-tion for RHR Pttnp 3AP35 could be delayed due to the auto-trar.sfer switch time delay. The maxinun delay would be 10 seconds.
This maxinun delay would occur if MO 3-10-16A received a signal to open and nonral 480V power to this valve is lost siruttaneously. Operating RHR Puno 3AP35 with no mininun flow protection for an additional 10 seconds over the '
present design would not result in excessive ptrrp/rrotor overheating.
Since this rrodification does not affect any radwaste system, the guldance provided In IE Circular 80-18 is not applicable.
The plant as described in the UFSAR is being changed by this nodi ficat ion. Appropriate Single Line Dlagrams will be uodated to reflect the new design. Sections 4.8, 6.4, 6.5, 7.4, 8.4 and 8.5 were reviewed to make this determination. Chapter 5 and Table A-3 l of the PBAPS Fire Protection Program (FPP) have been reviewed and will also be revised, r
IV 10CFR50.59 CKt6'GES, TESTS, Ato EXPERIMENTS:
- 1. This codification does not involve an unreviewed safety cues-tion because of the following: i a) The probability of occurrence or the consequences of an accident or rralfunction of eculpment important to safety previously evaluated in the safety analysis report Is not increased. The present valve operator con-trols, Indication, anc 480V pcwer supply for RHR Mininun Flow Bypass Valve MO 3-10-16 A are traintained.
MO 3-10-16A operates as p. eviously designed to 9Povide mininun flow protection for RHR Pu o 3AP35 during normal operation or design basis events. This rnodification adds a backup power source to this valve for an Appendix R fire, b) The possibility for an accide.nt or tralfunction of a different type than any evaluated previously in the safety analysis report is not created. RHR Minimtin Flow Bypass Valve FC 3-10-16 operates as previously designed. This nodification ensures minittun flow protection for RHR Pum 3AP35 during a loss of normal 480V power to PC 3-10-16A due to a fire in Fire Area 13N. PC 3-10-16A will norTnally be powered f rcm its present source. On a sustained loss of norms 1 4E0V power, an auto-transfer switch will operate and
- _ _ = - _ _ .. . _ , _ _ .. - - - - . _ _ _ _ _ _ . . _ - _ _ _ _ . _.
.u- \
\
l supply pcwer to MO 3-10-16A f rcm a Unit 2 backup source.
The E-1 diesel-generator feeds both the normal and backup power sources to the auto-transfer switch. This deslgn meets NRC Reg. Guide 1.6 and IEEE 308-1978 criterla.
The auto-transfer switch, auxiliary rmtor controller which controls MO 3-10-16A, and associated cable rerouting .
are designed and constructed in accordance with criteria I appilcable to safety-related and Appendix R safe shutdown systems. The cable routing associated with the backup source is designed and constructed in accordance with Appendix R safe shutdown criteria. >
c) This rrodification does not reduce the margin of safety as defined In the basis for any Technical Specification. ;
The RHR system initletion and operability recul rements as described in Sections 3.5 and 4.5 are unchanged by '
this modification. The operabl11ty of MO 3-10-16A is maintained to provide miniram flow protection for RHR Pum 3AP35 In the event of a fire in Fire Area 13N. ,
- 2. No changes to the Technical Specifications are reaut red based on the review of Sections 3.5 and 4.5.
i V 10CFR50.92 SIGNIFICANT HAZARDS DETEPPINATION*
A license a: endment is not reautred; therefore, this section is not applicable.
t i
l l
l
5-l e
VI APPROVALS:
Prepared By: . v DATE: h'U 'N Qesponsible Engineer)
Pfni/1$,E/,:h. DATE: h.lN2l$;'}
Reviewed By:
( D1 '. ndepe ent 'P',eviewer)
' DATE: I
/ '
l (Le'()Divisio Seef M9t/ Branch Head
~
DATE: 6 !2. 8 (Non-Lead Div. Respoisible Engineer)
< em fWu DATE: 0!P 2 H (NonM.eaf Div. Independent Revi r) !
DATE: c, )s ele 9'
' 'M d M ' '
Obn ' Lead Divi_. lor / ection/ Branch Head) d( ! DATE: 7 1!Ii3 (Nuclear GlEnvironmental Section Head) / /. j JDK: sic 1 sc10587m!30 2
(
Copy to: DISTP. CODE EESE-1 t s
I i
e l
l l
1 l
l
.m- ._ ., ,_,y7 y _ _ _ _ . , . _ . _ _ ,.__-_,,,,_,,,m, _,-,,,m_, _ . , , - , _ , , _ , _ , , , , , , . _ , ..__.,,_._._.,..-,_,,,,.-y,e.y..,,,,.,,y
. UCCAR CHANGE CONTRO.
, . v;-I~77; t/E3 Fes:P. Ecst:m At:mic Power Station
~
I da.t \ -
mes a '7.'2. 3 [ % jurC:rhe. _ ,REY. __
x:: :! :R!; !cN 01 b , ,,13 Qme .5.,o-I a D Wb '. - I C'(( A
- AT: I- W 'J9 FR:? 1!) !@.I:ith*AI!!N OAi! \ 7 ,! O b' f -
8 ntnR 17: Q . U. Lw .
R!r!K!x:!s: UC(AQ. I FP9
'~
(Use Accitional sheets As heeced)
E U [ ] UT3AR ChAN;!$ hCi RIQUIK!D (Indicate Secticns (nat .ere reviewef) 9 [y) UFSAR ChAhCES RIOU!R!D (Attacn UT1AR pages witn wercing/nwr.cering changes Nraed) '
PAGE3
$!CTICE ~ \
ICP!C ~d,\,, '
III7 WS $ p. sps g gf,w,y {3 {( d*,5 g
7, TA!LES PfF C'~q U e(,"b W C~3 ke cd'v dd FIGURIS
(!f acetticn 1 s: ate is reewired. use adettienal sheets of :::er)
[
FINA* UF5AR CXAN3!!
. RIC'.'!K10 (ATTA:X10 UT3sK FAG!3 VliM VOR0!hi/N'.'M!!K!h3 -
CKAN3ts KARK!: . U!! A0;!i!CNA'. SH!!is i
!T M:R! $7A:1 !$ R!OV!RI*.) i PA5!!
IOP!: $!?Il0N _
I!IT TAIL!s FIGUR!!
CAi!
. APPROYA'. 5Y: 1.
~ Res;:nsteie Aeviewer E.
. CATE U 2.
E.
Res::nsitie keviewer's Grow- Lescer er tran:n nea:
A*I 3.
Ras;:ns.itle hI3 In;ineer CAT!
4.
h!1 Ingineer.in.:nar;e FINAL F.!3 0' . Vi!CN !MP'.I.W.!hiD l
- U?!AF REY!!! N /
- ...e g FIY!!!: !Y:
5 Res;;r.sitie h!! Init?ett v
E (1mistt J.! . 11
.. *
HPCI- Pump Turbine Exhaust ;
PS2-23-97B HPCI Pump Turbine Steam Press PS2-23-6BA l HPCI Pump Turbine Steam Press PS2-23-6SB HPCI Pump Turbine Steam Press PS2-23-6SC >
I HPCI Pump Turbine Steam Press PS2-23-6BD TE-5941A HPCI Steam Leak Detection HPCI Steam Leak Detection
)1 TE-5941B TE-5941C HPCI Steam Leak Detection fN
[N " j "."\
s N
l I
i HPCI Steam Leak Detection -
/ W. ?. >
i, TE-5941D -
o i I t /
.__HP.CI_1.1..teraa.
Rd. NO 1-10 % A n:be Lys Control._Sta_t. .on_b b d C"i
- 3 0C0 4EX . . .. "
i L r%t S CHN 3%9 ~
(c) ~Pos Writec F: e in A?e'a l
(1) Ignitien of electrical cabling in cable trays (an l
unlikelv c::urren:e in the absen:e cf a f tre source l' external :: the cabling since it is cf the self-ex inguishing :ype).
2 and 3 - P.HP pumps, HPC: pumps M-0< 850 (2) Lube oil from UnitsEre:irculating pump M-G sets, recir:ulatin t lube cil pumps, P.CIC pumps either leaking on : h tin; c.
! with subsequen- 1;..ition cf the oil or an over ea i
the pumps causing ignitien of the cil.
(3) Char: 0al filters in -he SGTS air p;enur.
t l
f (4) Spent :harcoal filters in filter ro0m 235. Orage area I
(5) 1;nition Of tras* ' -Se radwaste trash s: ;
from an external source. l (6) I;nition cf paper in the radwaste con rcl roe- f ro- an I f ex ernal seur:e.
f 71 , gg 3 g;ggy, 7ir,Suppres,icn (d) Consequence 1 smoke,;enerated by a firealarm will a..u.:iatien a::!vate smoke dete ,
,;je -ause anUP:n audible-visual 1.. thecf an alarm f rem an f re:eip I"a ;. ;" e*7 a
n .r e , ::::',
- he are9 the fire brigade will be dispatch'ed *:Tnl
[7'"8 .sh ,.he . ire.
- _g~ g'p;P, rc0.s will a
- :ivate smoke the ftre alarm de:e::er's whien I
- ^"'a...
am g
e-v.sual alar- annuncia:1cn at
- P. e v .
C, 5/E6 ,
l 4 .: . . . , , . i F
b
- i I
4 I
I l
. , , _ , . _ _ - . , . . ._ _-_.-. . _ , . ,___,,,mm.., , _ . , . _ - . _-. _ , _ _ , . _ _ , _ . _ _ . _ _ - . , _ . _ , . , - . . , , , . - . . ,
Emcrg ney Switchgear Room 267 E.3.25 Fire Arec 33: (Elev. 135'-0*).
Area (a)
Structural and Architectural Design Teatures ofEatinc Fire Construction 2-hr Cor. crete r.asonry units 3-hr Walls: N -
2-hr E - Reinforced concrete 2-hr 5 - Concrete masonry units W - Concrete tasonry units 3-br floor: Reinforced concrete 3-br Ceiling: Reinforced concrete Daer cent.ecting to fire area 32 / 7"'\ .
Accer : boer cont.ecting to fire area 50 A:s LLk6 Us.t 3 ,___;
Related Components in Tire Area
- f. h ) Pb 4 c.
/ ,
iT. wegency Auxiliary Switchgear i / J 4 I vew Ec. uu.dtr sam -,--
8
/
,/
- . 40'.or Control'C_enti ~r /
( c ' Pe si u.a - ;ikely c t he le- t.
'5 r ';:: cal cabling in cable tray, (an unthe ). a sence c
.a '#-er cable'is cf the sel!-extinguishing type ot,ur. . .
I OESIP ,
> Suppression (d) Conseque.. o of T're with Active Fi:
a fire vill activateannun:iation smoke detectors at 0f the The Sroke generated byill :Tuse an audible-visual Upon alarre:e!7 ,
sh'en s '. . . ce fi-9 annuncia:c :n the ta.n :en:r:1 recr.the plant fire brigade n the control root, En3 .lbr: to er.tinguish the fire.
dispatcheu (ei Effect of Fire on Safe Shutdown associated vito Cables Tire area 33 centains cables and equipmentand C fer Units 2 and 3 shutdevn rethods su;7:r:
A, 3,shutd;vn re:hed 3 :: f:
required ::
are encapsulated oy a 3-hcar-rated fire barrier c , encapsulated, cables that are n0:
be taken to recover anv functions Equipment asso:!a:ed with shutdown method that eculd be lest.C loc 3 :: lo:ated ken componen:
this fire area either have a redundantoutside 7neref:re,the fire area or to recever any fun::!cns that could be lost.
F.e v . O, 9/!f 5.3-95
_ d
i l
l
$+ (Page 8 of 46) i
- TABLE A-3 (Cont'd) l i
- Hot Cold Tire Shutdown Shutdoq Area Methods Equipment Component Description __ _
i Number _ -
3C
, 12 Core spray pump D 2A,2E,2C,2D Unit 2 3DP37 HPSW pump D 47 3A,33,3C,3D Unit 3 ;
3DP42 -
i I
2 3A t 30E32 RCIC barometric condenser i 2
35,3D 1 HPCI auxiliary lube oil l 30P26 - - - '
pump 2 3A RCIC vacuum pump l 30P46 j 2 3A RCIC condensate pump l 30P48 33,3D ;
- d.i ttt 2 r
' a.A -> '3 053 7 HPCI turbine 1s m
,U^^
, . . 3. .
t m i
---up. ~~ikh.-5.3C (b .% . , . ,
) I.i'sc~es:
5 [( ~'-[.dd'._Yi i. N, ~E(,4to V 4C_"c7 ".2 e ,
9
...,...,a,--
~
.E
- e. Un;;;
nP3n unit intertie valve 3A,35,3C,3D
, ~i oic..a 2A,23,2C,2D Uni- 2
- 47 2, n.<... 3 HPSW unit intertie valve .A
- , 3.=. , r-o.-
i 5163
-- U . .1 - 3 2 -
t DPI3-?0-179 P.HF/HPSW dif f erential l pressure indicator Unit 1 10 3D DP'3-10-179 RHP/HPSW dif f erential 4
- y. essure rans.itter l 2$ 2A i
PCO-13-51
?.CIC fl0w 000t;0119: .
f .:. .. = - , . --
f
.T-~. ..t.a.:
.. . . . .r st.
. - + .... .........e.
...... 9
- *$ 3A 1
"C3-13-91 P. IC flow :entr:11er 25 33 i
l
- C3-23-10S HPCI flow contr:11er *A,*3,2','? U~!" -
l "5 .
i.A.,.s=,te Uni- 3
(-
f ?**-10-132A H?SW flow indi: ster .-
4 2$ 2A,;E,20,0? .-
U..
n !, ". i.
u.... .
HPSW flow indicater 3A,,.,, .a . ,as
! TI:-10*1323 a .
')
?.e V . O, I/IS 1
i 1
e
)
_ . - - - - . . , ~ - . _ - _ . - . ---,_.-nnn-,--.n -- . , . , , , _ - - . , , . , . . , _ . . _ ___ _nr,_ , ._v,_~,,. , , - . ,,p,..-,
i
(lage if' cf 44)
A3' E A .3 ( Con t ' d )
Hot Cold '
s Fire Shutdown Shu t o c>wn Eculpment Area Methods _
Nu.ber Cx.conent Descriotion Unit 2 2A,23,2C,2D :
o 460V ac motor control 39 3A,35,3C,3D Unit 3 HCC20359 2A,23,2C,2D Unit 23 center
] l 37 3A,25,3C,3D Uni e
MCC20360 480V ac noter control center Unit 2 j 2A,23,2C,2D 460V ac meter control 2
3A,3B,3C,3D Unit 3 I HCC30336 center Unit 2 i 2A,25,2C,2D j 420V ae rnoter control 13N 3A,3E,3C,3D Un!* 3 HCC3'0337 ,
center 2A,25,2C,2D Unit 2 4
135 3A,23,3C,3D Uni' 3 J
l MCC30338 450V ac mo2er control ,
center .n n.... .
i j gg ..r, , .. ,3as .
n ,. t
?
4 e. rd. a meter gen.;gt. g.,:.,se.,tm . - V... .
'l v*ata=se a
C,- .,,
.n ..
- \ '
- i. t. .a,.-,.s,-- ,. 3.-
i n. .
, . ' .
9.A, 80 meter Con'a.o. g,e. , ,. =. . , 3 . e. , g --% . . .
. -:4 .! .,\ wenter n.. .. ., ..
l
? / _ U . .t 3,\ S. .g
..,.=,w.,.%
.6 .- ..
v.... ...
.4&OV a m: ,,0; cong o1 1s te e n f :. =.J -e s , 1. m.
e
. n. 6 y" *e *4*D aV - hya l i
/ ,,,u_.
. e ,, + Q3g g )c d. -
t
/ . v .s s. . .yu. .s , . \./~. Q k %
t O c,. n s.g *- , ,.s,t\ w.eMt~
t-
..~ .
-- f o , t = , t. ~ , t m ". ..
5-% *
> - ~- . ,.
w.-.r-- - :. = 6 : T3TrMWva:ve-- -
m t.n s -
, w...- --
!v ,,y, ~ -
,s.,. .
f
..n
. , . = , 3. r. , 3. ,. t 1 .. Sluice gate
- v. a. a.
s.A,s.=,se.,.im . - r. . 4...t .
l "v.~'dl.e n.. .. ,. .- -
,5 ...,,..%.s,,--
n . . . . , .
t.
i l
H.., . .5 a
.e...,.e
- n ,0
,a- . . . . .
4 n,. .
e5 . t.
i 1 u.
'"~~a=
..... Slui:e gate i
. A,t=,.te.,.so s
j .
. ., n.. .. ,. .. e.
, ,e 7,. , .e : , . . . . -
y w a.
4000 i ** .. er* f e vgly, 9. .
- t. A , s =- , t. a .
"..s..
.. . t. l 1
'* )
J
. t' a
.6,.
a- ,.r.,--
a
.- '.' 8 *.. 9 I 4
4 "v. # ~ .d ', ,' '
N E S'n' d!Scharge valve !
J
.g gay !
,1
- s J
I 1 w e n:
r I .e.. . ., se.. ,
i I
d i 1 1
, l
' l l
==,,--,.--rn.~~,,,p-p.- -w----,- ~,-.--
sy y ,w r ncge-e r-- -nyy.,,mmm,,n,,, m ,- w n g e- ,, e m m,,m_,.m.,,-mp.,mwe,,. ~~~---+-w----r~n
ALARA REVIEW CHECKLIST, REV. d l
3 Responsible Eng. [ O. Ve 3 a -
l S:ation hM P.$
Unit i l Mod i 2.2.9 [ n 4\br.nc1, f4_u- S .n[ 4 8e HO H 0-( l Il Mod
Description:
l.. is located in high Non-radicactive equipmen: that
- 1. areas) increases worker To lessen radia:!cn environmen:c ("het" exposure during operation and maintenance.having high reliability see and
- nts exposure only equipment low maintenance /calibra:Acn requirements shou.d beDo in these areas.
locate non-radicac:ive equipmen: in "hot" areas?
l No Y Yes l If Yes . Erylain _
l l- -
l areas in non-:adi ca:-ive
<-. aceme..- ef "ge:" equip::.e..:
I -.
in : eases ::ke: exp:sure f:: a *. '. 4 :- i v i -cap i eu:s e:1::ied sy s . ::-ru:
Shielding and p;cvisions :: Does pn the area.
.eakage can ::inimize exp:sure and centa: ina:ic ..in n:n-:adicactive this cesign 10: ate "ne:" equipmen-a:eas?
l N: Y_ Yes _
i :f Yes. D:: *. s i . _
l_ _
s i
I
.r.
.::. ..-a.e
- ~.
- ;.= . . . . .
i
j- .
(crud) in pi;;ing ,
- 3. Deposition cf activation products !cr all plant ;
i systen;s results in increased exposureThe f ollowing design consideratio workers.
minimi:e crud de; ssition. i 1 a. eliminate low spots by sloping all horizontal runs '
l .
eliminate elbows b.
- j. l ,
l
- c. use burt welds instead of socket welds 9
l provide flush and drain connections for equipa,ent
- d. i and piping runs l promote
- e. eliminate activationthe (e.g. useStellite of materials contains thatCobalt unich is t the mest significant activation product). :
Does this design f ail to incorporate tne above ,
considerations in radioactive systems? ,
i ,
t 4
No X Yes - t i l i
- l
- f Ye s . t>:elair. ,
1 .
T l _
l --
I.
I i i [
4 !
I, sr.i eld .ng 'ry
- 4. Does the design change perranent ;. .a n t l l
' adding penetrations er cutou s in the snie*. ding? i 4
b l
N: Yes _
l 2
l If Yes. E).Ol a i ". >
s
) ; .
l 1 :
i 4
.<.=i tya . : :f a i
-- s..
. v... . v !
a t I
i l l
! f i (
f i
I ._ _
- 5. N high : mal ventilation radiation areasflow in is item order non-radioactive areasof Does thistodesign minimizealter thethese spread airborne contaminants.
flow paths?
l No Y Yes j :f Yes, Exclain _
l I _
l i
a
.I
- 6. W::ker exp sure during routine maintenance in high '
considered:
se it can P cvide flanged nne::icns en equipment a.
be ::ved := clean areas fe: maintenance.
- b. Iquiptert/ materia; *.aydewn areas sneuid be provided l
cc side Of the ni;. rad areas.
l p'.a:f:::s vs.
e:e::i:n Of
- c. ns:a.a:icn of permanen 5 . 3,.4 2.,... . . . , .
emp::ary shielding.
I
- d. 7:: vide fe: :ne e:e :icn cf h: ea t.. .; ai
- e. Investiga:e :ne ;;;ximi y ::
- nne::icns.
Does :he design fail :: 1,.:: p::a e the ab:ve !
- cen s id e r a:i ct.s ?
'f I u
e #
l w
es s .,e. .. .. .-. .. .. ..
3 1
i
( ,
I
-- , /
3 s.
./:..> t., -
l' O...
... .. .. S i
r a
4
Branch for Any ite.sm n.arked Yes must be referred to the Nuclea:
cc: p;e:ier. Of See: ion :1.
~
- b. D . (b.t, . Date . 2". ' -
l Prepared by:
(J f//f NY j Tseviewed by: 7[ 7d fb Date j ::. *ecuiremer.:s/resciutions of 1:er.s 1-6 marked Yes.
h1 l
1 _.
I I
p { 6. Oate repared '): ~(:;;;. e a : 5. a r. r. )
l' App::ved :): I il Oate
,sup.. I.:. ns)
A. 4.n ac . l: (i. :.d; l l 00: I-:- r.dus::;a
\
.v-t.\,
i.
e f.aM ,,ae a f.d. . * * \ )
5*a*ict Supe ir.:ende.: 4.I. Cadie ' ?2 6 P.$)
CA: ( :::ype =so ;
-i. .D . TOs %. QM l
' ,. :. ..g-9 T 4 :! 4)
..'.y. . . .
1 l
l
.f '
FIRE PROTECTION REVIEW CHECKLIST, REV. b l Responsible eng. M 0 . %tmo m Station __ Unit i 3 MOD i N I. Mod
Description:
hdecuk Le Swb w b No 5-t(7-l(cA
- 1. New penetrations through rated fire barriers are being created. Existing penetrations require removal or (See r modification (not including cable penetrations).
Architectural Fire Barrier Dwg.)
No X Yes !
r Description, location ,
1
- 2. New equipment represents an incrcase in the combustible l loading to the site. Items to be considered are lubricants, fuels, combustible gases, bulk gas storage, '
insulation, plastics, etc.
No Yes N i r
List quantity, nature, and location of combustibles,q. [
(,t-sv.') cNu :
- AO Men ef e. . Met # o h. P at , e M.( CA obb c, A l t
,, n A. ws 3., .. m i< i s r%. . ,L., sut.L..- '
bu ( m isN
' rsc,osvt
.i . Relocation or addition of any safety related l I
equipment / component / cabling.
No Yes Y a !
Description Oc M (As c.ucc.v/ wa 3.go.qhALe x,.\\ k h u A d b4 "
i Mct m o um L.~ M.t-sa ca.g kr MM -* ~ M ,
l
' .+53 mout .ev a_ 3, agte- m n . s ars _ , w e e, 3 ~ -- i
- 4. % na t4 U "
Sw %. % I
- 4. Relocation or addition of any safety related l
equipment / components / cabling identified as safe shutdown in the FPER and circuit and raceway schedules.
No Yes Y l
Description Seo Ma "3 e.h. . * % d\.\ i, .s . a Mw cn \.
C i 1
ke e -s Mrt t06% ,,, . o -n>.k. ,.3 t d. A h ow 4
n\t u nuk i o e ca.m e 6 Mc wt0-n A V . n.,
4ku n.da - ires f u. ss.'4 A .
EXHIBIT 3.3-VI 4/86 (Page 1 of 2)
- 5. Will the codificction interforo with tho offoetivonoss suchof as existing fire detection and suppression equipment; require modification to sprinkler piping, Is thereor block a or suppression sprinkler head or fire detector?
detection equipment within one foot of new equipmentWill access to detection:
installed for this modification?
suppression; fire dampers be compromised?
No M Yes Description Prepared by: h l ~. _Date b 5'M Reviewed by: M !-f _ Da,te f////96
! Any items marked Yes must be referred to the Buildings Facilities Branch for compl'etion of Section II. ,
I. Requirements / resolutions of items 1, 2, 3, or 5 mar,ked Yes. L ?.L tl T . 5 r uL 9 cc, e oc.e.o Nod me_ Anc+1 f Qc c- T? 8b ou i d e%-r h4 .w sdee ec,e l 0 0 C- s. Nw 9eeger_ncv Ar Maues.
op -r sA W e.e_ ,
Prepared by: N _ Date G//7/bN (B . F . Branch)
Reviewed by: [bb Date -
(c I
II 600 (F. 7). Branch) '
Raquirements/ resolutions of item 4 marked Yes. JS6Fhd[cP/ / 4 M4Ju07G~$r W, v ]l.
i
- Prepared by
- _ (O d 'Mf / Date 8[9hf C .g g p + .
(E.E.' Div . )
Reviewed by: Nb b. Date 3b
tt
[
l u j, ,
- (E.E. Diiv.)
Approved by: (( Date d!/7 [_
(Supv. Engr. BFB) / /
J
- ct E-I-C Industrial MPE 4
EPE Station Superintendent DAC (Doctype = 197)
Q .Q oC WO EXHIBIT 3.3-VI 4/86 (? age 2 of 2)
)
4
- I
~'
No. FP M a O_h)
- Fact 11ttes Branch FPRC Evaluation Form Rev. 1 3'% -I to Fire Area / Zone ? - SR Mod. 2186 Elev. ,_Lfi' Station VOxs-6 Resp FB Eng PDF >
Date 6 / 4 /w.
Items Checked Yes:
1.1. (1) If PBAPS, require seals to be Installed per pg Spec M-610 (2) If LGS, require seala to be installed per Spec M-629 j
1.2 (1) Will increased loading inpact on a ccrrbustible free zone .M.E g,% 6-W be.e. Si 4 a) PBAPS - 1. FPP Set!:n: S.O -
- 2. FPP Sections 5.3.e
- 3. FPP F.lgures 5.3.f b) LGS -FPER Sections 5.4.e
- - . . -, .... . . ._ _. .__ c) _3 f 3 t,_3 2 .1~. a ' &~ b i nc l ude ' any - I t ems ma r ked y e s , ' - - ~- ' ~ ~ " ~ ~ ~ ~
infcrm the responsible engineer that this is not acceptable without additional analysis by Electrical Engineering or fireproofing the hazard.
d) Calculate quantity of cerroustibles to be added in units consistent with those given in the FPP for PBAPS or the FPER for LGS. Aw t u% ein e u , a A* e -
r c.ee ww 3 w.:, a oc % A. r .n um ee ato
' Nuts sw A+ e e.sc soe c r o 45 A m (.- n o +%D --
w vaAA a '. , __
(2) Will increased ccrrbustibles be added to an area containing safety-related eculpment/ cables wtilch is NC not protected by automatic cetection?
!! yes, add detection, recuest an exer otton pelor to approval of work or relocate ccmbustibles.
Nsecr w cv % io rict. .s er a f t. ,.'e a. 2 -st<.
, t. M 4 ~~ ~ f Lo .
. . , 6 .,
+
(3) Will increased ccnbustibles cause ccmbustible ,
loading to be in excess of a requested exemption PC for PBAPS - refer to FPP Sections 5.3.f's (se c. 3 7. . % .e() [
If yes, determine if increased loading defeats the l Intent of the exenotion request. If no, Inform if the yes, r NRC in accordance with established mechanism, i request an exanption prior to start of work. !
l (4) Will the loading be added to an area in which there ,
is unprotected structural steel? ,
I 6
a) Refer to PLC Structural Steel Su1 mary !
Calc tk. PIA Yes I Go to 1.1.4.b i
te
/ ,
I Go to 1.2.5 I
b) Determine if increase is greater or eaual i to 10% of the ortoinal_ fixed loading the cale --
[
- - . . _ - . .. . ._. . . . . . j 3. ba s e d on - - ~ ~ ~ --- -
i l
- 1. If no, go to 1.1.4.d -
- 2. If yes, go to Structural Steel calc f and re-perform analysis. After completing analysis, go to 1.2.4.c j t
c) Did the Increased loading cause steel to fall? l I
- 1. 1i no, go to 1.2.4.0 ,
r
- 2. If yes, determine corrective action and l inform responsible engineer to go to I 1.2.4.d i I
l l
l l
l J
l
e - ,
(d) Update analysis: If loading is greater than 10%, add an additional 10% or the total arTount of increased loading which causes the steel to fall, which ever is less. If (original 10f) t so that the next calculation will be based on the original 10% less any subsequent nods which have added ccnbustibic nuterial to the area.
(5) Does increased loading represent an unevaluated hazard to safety-related coulpmnt?
V a) tb, go to 1.2.6 Gu A7 .O .D b) Yes, go to 1.2.5.c .
1 I c) Determine if there is any adverse Inpact l and any additional fire protection enhancements rcQulred.
f l
1 f (6) Af ter satisf actorily resolving items 1.2.1 through !.2.5 on this evaluation form and items !.3 and I.5 on the FPRC, forward this evaluation and the FPRC to the respcnsible Facilltles Branch engineer for the FPP for PBAPS or the 1 FPER for LGS to revise the appilcable sections of the
- - - ~ -- ~ - respective rescets arreculred by this- evaluation.-- l (7) Sections of FPP or FPER reviewed.
Q?Ccd 4 4 ta Cic rwk 6. L1 4 6. h ? 5 (D i s cs c, - b
(!) !s en LDON (LGS) or a UFCCF (PBADS) required to MD specifically address Fire Protection? .
Eesocrstbility for ccs clettn; (if apollcable).
(9) Ccmmnts:
r
- _4
, ' ,,*. ' ' , ,1, (10)
Conclusion:
AA
% ra cs,w e, ws. w a. nv .e s oc.c c mm . Av.
for<c- av Tin rs e.c renveevio D6% %
Ar m e c, e.,c.au w .
(oww % wv
- e r- co wra.wcc> is A RE 9 o_
ch Tx puo wua ecr ec c.ommta.o A G atwtuee \
b@h \W1o 4 sve%M h Ih (9 OPAG- *
)N T 4 g. C.c t*P ubT*MtE
$'"*' C " #""'
4 ccas (D Db v.cv w e.m . r + Fm Tuc
% us c%.
JCP/vvg/01088805 i
i i
I 1
l I
l