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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 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 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 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 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 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 ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl 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 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 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 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 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 ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl 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 ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 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 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs 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 ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 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 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed 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 ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed 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 ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) 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 ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed 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 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 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 ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl 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 ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 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 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl 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 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed 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 ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) 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 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 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 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint 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 ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs 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 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error 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 ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 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 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure 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 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys 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 1999-09-09
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- Stat'en Support Deptrtmtnt y
PECO NUCLEAR esco coe uv comneev Nuclear Group Headquarters l
A Umr or PECO EntRcv Q yry fad July 1,1996 Docket Nos. 50-352 50-353 50-277 50-278 l Ucense Nos. NFF.39 NPF-85 DPR-44 l DPR-56 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 ,
l
SUBJECT:
Limerick Generating Station, Units 1 and 2 ;
Peach Bottom Atomic Power Station, Units 2 and 3 Request for Approval to Cheage the Quality Assurance Program >
Description by Changing the Fire Protection Assessment Frequencies Gentlemen:
This letter is submitted in accordance with 10CFR50.54(a)(3), which requires prior NRC approval for any change which reduces the commitments in a previously accepted Quality Assurance Program Description (OAPD). The Quality Assurance Program is described in Appendix D of the Peach Bottom Atomic Power Station !
(PBAPS) Updated Final Safety Analysis Report (UFSAR) and Chapter 17.2 of the ,
Limerick Generating Station (LGS) UFSAR. The OAPDs commit PECO Energy '
Company (PECO Energy) to perform three separate assessments of the Fire Protection Program. These assessments range in frequencies from once every 12 months to once every 36 months. PECO Energy is proposing to consolidate the three Fire Protection Assessment commitments described in the OAPDs into one commitment in each OAPD to be performed once every 24 months. ,
The proposed changes to the LGS and PBAPS OAPDs and their affected pages are i provided in Attachments 1 and 2 respectively. !
' Assessment Descriotion The current Fire Protection Program assessment frequencies are based on NUREG-0123, " Standard Technical Specifications for General Electric Boiling Water Reactors',
Section 6.5.2.8, " Audits', items h, I, and J. These assessment frequencies are g lo i described by Generic Letter 82-21, " Technical Specifications for Fire Protection Audits." Currently, these assessments are invoked by three commitments included in PBAPS OAPD, Rev.13, Section 17.2.18.1.1 and LGS OAPD, Rev. 5, Section 17.2.18.6, as follows. ll/ fM.
9607080263 960701 Ml /t/(kM//fol$ / /
k? _. .-
Idllbb}lt&ln6 I I
July 1,1996 Page 2 Assessments of plant activities in the following areas shall be performed under the cognizance of the NRB:
- g. The Fire Protection Program and implementing procedures at least once every 24 months.
- h. An independent fire protection and loss prevention inspection and assessment shall be performed annually utilizing either qualified offsite PECO personnel or an outside fire protection firm.
- l. An inspection and assessment of ths Fire Protection and Loss ,
Prevention Program shall be performed by an outside qualified fire !
consultant at intervals no greater than thiriy-six months. ;
i The current sections of the PBAPS and LGS OAPDs were evaluated in accordance with 10CFR50.54(a)(3). No other references to Fire Protection assessment l frequencies are described in the OAPDs or the Fire Protection Program. The affected pages of the LGS and PBAPS OAPDs are contained in Attachments 1 and 2 respectively.
Proposed Chanae to Assessments PECO Energy requests approval of the consolidation of these commitments in the following areas.
The consolidation will change the frequency for the independent fire protection and loss prevention inspection and assessment from once every 12 months to once every 24 months. This frequency change is based on the fact that during the interval between fire protection assessments, an on-going surveillance is conducted to prov'de l progressive assessments of functional performance.
The consolidation will change the frequency for the inspection and assessment of the Fire Protection and Loss Prevention Program performed by an outside qualified fire consultant from once every 36 months to once every 24 months. This change ,
facilitates the commitment consolidation.
The frequency for the assessment of the Fire Protection Program and implementing !
procedures will remain the same.
Consolidation of the noted commitments will require that the Fire Protection Program and implementing procedures, including the inspection and assessment of the Fire Protection and Loss Prevention Program, be performed utilizing an outside qualified fire protection consultant at least once every 24 months,
July 1,1996 Page 3 Reason for the Chanae The purpose for consolidating the commitments is for clarity, as well as appropriate allocation of assessment resources based on evaluation of plant functional area performance.
The consolidation is prompted by the guidance provided for assessment frequency by NRC Administrative Letter 95-06, " Relocation of Technical Specification Administrative Controls Related to Quality Assurance" under the Reviews and Audits section.
The consolidation of Fire Protection assessment commitments will r0sult in an increase in the Quality Assurance Program effectiveness. Currently, the subject assessment area is regimentally scheduled for assessment on an annual basis w!thout due consideration of the need for the assessment in view of performance as indicated by empirical data, events, and trends. This can result in an inappropriate allocation of assessment resources when other areas are in need of an assessment as indicated by performance data.
Assessment activities, to be effective, must be performed on a frequency commensurate with tnelt safety significance, and with due consideration of performance data. The change in frequency for the noted assessment areas to at least once every 24 months will enable NQA management to schedule Fire Protection I assessments and allocate personnel resources based on performance data. This I mode of operation is substantiated by the fact that during the interval between assessments, an on-going surveillance is conducted to provide for progressive ,
assessment of functional performance. j l
The overall net effect of this change is that over a six-year period at least three l assessments (all involving an outside fire protection consultant) will be required.
Currently, six assessments (two involving outside consultants) are required.
Procram Continues to Satisfy Criteria The proposed change to the assessment frequencies will continue to satisfy 10CFR50, Appendix B and will be adequately described in the respective OAPDs. The purpose, I scope, and thoroughness of the current Fire Protection assessments will not be l affected by the change. Management oversight of the assessment process will not be diminished by the change.
Changing the frequency of the independent fire protection and loss prevention inspection and assessment to at least once every 24 months does constitute a reduction in commitment relative to the frequency as described in the OAPDs.
However, this change will not reduce the effectiveness of the Quality Assurance Program, nor will this change reduce the PECO Energy commitment to quality or to compliance with 10CFR50, Appendix B on the following basis:
- 1. The Fire Protection assessment will be scheduled based on empirical performance data such as trends, events, and surveillance results.
l July 1,1996 Page 4 f
- 2. On-going surveillance is conducted during the 24-month frequency interval that provide for progressive assessment of functional performance.
- 3. The allocation of assessment resources will be based upon performance data and thereby provide for timely assessment coverage of areas which warrant oversight attention.
Donclusion The proposed change in assessment frequency does constitute a reduction in l commitment as described in the OAPDs. This reduction requires NRC approval prior to implementation pursuant to 10CFR50.54(a)(3). The efiectiveness of satisfying 10CFR50, Appendix B, requirements will not be reduced as a result of the change.
Because approval of this change would impmve resource allocation and the effectiveness of the Fire Protection assessmeat, we request the NRC's prompt attention to approve these changes. If you have any questions or need additional information, please contact us.
Very truly yours,
- 4. 0. ,p.
G. A. Hunger, r.
Director-Ucensing Attachments
! cc: T. T. Martin, Administrator, Region I, USNRC W. L Schmidt, Senior Resident inspector, PBAPS, USNRC N. S. Perry, USNRC Senior Resident inspector, LGS R. R. Janati, Commonwealth of Pennsylvania l
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l ATTACHMENT 1 LGS UFSAR l
LGS UFSAR
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17.2.18.6 Assessments of plant activities in the following areas shall be performed under the cognizance of the NRB:
- a. The conformance of unit operation to provisiens contained within the Technical Specifications and applicable license conditions at least once every 24 months.
- b. The performance, training, and qualifications of the operating staff at least once every 24 months.
- c. The results of actions taken to correct deficiencies !
occurring in unit equipment, structures, systems, or '
method of operation that affect nuclear safety at least once every 24 months.
- d. The performance of ~ activities required by the operational QA Program to meet the criteria of 10CFR50, Appendix B,
.at least once every 24 months.
- e. The emergency and implementing procedures at least once ,
every 12 months. i
- f. The Security Plan an'd implementing procedures at least once every 12 months.
- g. The rirc Prctcction Program and implc=cnting precedurec at 10 0t cn c cvery 2' =cnthc.
- h. An independent fire protection and lecc prevention incpcction and accccc=cnt chall bc performcd annually utilicing cithcr qualified offcitc DECO personncl cr an cutcide fire prctcction firm.
- i. An inspection and accccc=cnt of the rirc Prctcction and Lccc Prevention Program shall bc perfor=cd by an cutsid:-
qualified fire concultant at intervalc nc greater than a..__...,. u .. ___ u_
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p^new;g~h The Fire Protection Program and implementi. . .ng procedures,'
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including an inspection, and assessment of the Fire Protecticn and Loss Prevention Program, shall be performed utilizing an outside qualified fire protectiori ' ' ' " ' ' " '
cons,u,ltan_t, , at l,ea,st, once ' eve _ry~24_ months, . ~- ~'
_,< s s i h. The Ra lolog a En nmental Monitoring rogram and the results thereof at least once per 24 raonths.
k i. The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
4 k. The Process Control Program and implementing procedures at least once per 24 months.
17-2-56 Rev. G6 4-/46
, 9 ATTACHMENT 2 PBAPS UFSAR 1
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PBAPS l- ,
,17.2.17.6 Types of quality records with minimum retention l periods are listed in Section 17.2.17.3. It should .
l be recognized that the nomenclature of these '
records may vary. For records not listed in ,
Section 17.2.17.3, the type most nearly describing !
the record in question should be followed with !
respect to its retention period. !
l 17.2.17.6.1 NQA and other organizations responsible for records control are defined in the administrative and implementing procedures.
17.2.17.7 Original design, manufacturing, and installation records and specifications shall be controlled and maintained.
17.2.18 Assessments 17.2.18.1 Assessment Program 17.2.18.1.1 Assessments of plant activities in the following areas shall be performed, under the cognizance of the NRB.
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once every 24 months.
- b. The performance, training, and qualifications of the operating' staff at'least once every 24 months.
- c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety at least once every 24 months.
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of 10CFR50, Appendix B, at least once every 24 months.
- e. The Emergency Plan and implementing procedures !
at least once every 12 months. j
- f. The Security Plan and implementing procedures at least once every 12 months.
i g. The Firc Prctcction Progrcm cnd- implcm nting proccdurcc ct lecct once C/ cry 21 monthc.
- A i
D.11-47 Rev. -14 14 )
11/05 i i
1 PBAPS
,, .. h. T.n indcpendent fire protection and lecc prevention inspection and acccccment chall be l performed annually utilicing cither qualified Offcit: PECC Encrgy perconncl Or an cutcide fire protection firm. l 1
- i. An incpcction and acccccmcnt of the Firc l Prctcction and Lccc Prevention Program chall bc performcd by an cutcide qualificd firc eenet*Ltant at intervalc nc grcatcr than 2C month y l
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i h. The- adiological nvironmental. onitoring Program and - the results thereof to meet ~ the provisions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per 24 months.
k i. The Offsite Dose Calculation. Manual and implementing procedures at least once per 24 months.
1j. The Process Control Program and implementing procedures at least once per 24 months.
m k. Any. other area of facility operation considered appropriate by the NRB .or - the Senior Vice President and Chief Nuclear Officer.
17.2.18.1.2 Assessments shall include verification of compliance and effectiveness of implementation of programs, procedures, regulations, and license provisions in the areas audited. Written reports of such assessments shall be transmitted for appropriate action to supervisors having responsibility in the areas assessed.
17.2.18.1.3 Assessments shall be performed by NQA personnel or by specially selected groups or individuals who have no immediate responsibility for the activity they assess and do.not, while performing the assessment, report to a management representative who has immediate responsibility for the activity being assessed.
Timely follow-up action, including re-assessment where appropriate, shall be taken when deficiencies are noted.
17.2.18.1.4 The assessment program and schedules shall be reviewed semi-annually by the NRB.
D.11-48 Rev . 3 14
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