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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F2241990-11-0909 November 1990 Forwards SSFI Repts 50-277/90-80 & 50-278/90-80 on 900917- 1003 Conducted by Corrective Action Review Team.Corrective Actions Generally Acceptable W/Some Weaknesses Noted IR 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058G1541990-10-31031 October 1990 Requests That Util Furnish Ref Matl Listed in Encl 1, Ref Matl Requirements, for Administration of Licensing Exams & Evaluation of Requalification Program Scheduled for Wk of 910304 ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20062B8211990-10-11011 October 1990 Forwards Final SALP Repts 50-277/89-99 & 50-278/89-99 for Jul 1989 to May 1990.Improvements Noted ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable ML20059M6561990-09-22022 September 1990 Ack Receipt of Util Re Corrective Actions Taken in Response to Insp Repts 50-277/90-13 & 50-278/90-13 ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 ML20059H0701990-09-11011 September 1990 Requests Addl Info Re Audit Rept Distribution,Per 890711 & 900420 Application Request for Removal of Organization Charts from Tech Spec Per Guidance Provided in Generic Ltr 88-06 & Miscellaneous Administrative Changes ML20059K7211990-09-0606 September 1990 Forwards Safety Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27 & Notice of Violation ML20056B2691990-08-23023 August 1990 Forwards Request for Addl Info Re 880126 Application for Amends to Licenses,Revising Tech Specs to Provide More Restrictive Limits on Emergency Svc Water Sys.Response Should Be Provided within 60 Days of Ltr Receipt ML20059A6581990-08-16016 August 1990 Requests Discussion of Measures Considered &/Or Taken to Reduce Amount of Time Needed to Obtain Effluent Sample Analyses Results,Per 870121 Application for License Amends to Licenses DPR-44 & DPR-56 ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20056A5011990-07-30030 July 1990 Forwards Safety Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702 & Notice of Violation ML20055E1711990-07-0606 July 1990 Requests That Licensee Provide Data on Channel Box Bow Vs Exposure Associated W/Methods Used to Account for Effects of Channel Box Bow During Second Bundle Lifetime Channel Boxes, Per 900425 Response to Bulletin 90-002,within 30 Days ML20055E9611990-07-0505 July 1990 Requests Addl Info Re Util 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20055D0721990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matls,Listed on Encl,Should Be Provided by 900724 ML20055C8761990-06-15015 June 1990 Forwards Safety Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Increased Mgt Attention Warranted to Ensure That Instances of Failure to Complete Surveillance Testing Identified & Corrected ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H8041989-10-0505 October 1989 Grants Termination of Requirements Set Forth in Section VA of Order to Permit Operation of Both Units at Full Power ML20248H1361989-10-0303 October 1989 Forwards Unexecuted Amend 22 to Indemnity Agreement B-28, Reflecting Changes to 10CFR140 Re Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G2291989-09-29029 September 1989 Forwards Safety Insp Repts 50-277/89-21 & 50-278/89-21 on 890901.No Violations Noted.Insp Concluded That Improvements in Radiological Controls Program Have Been Slow.Addl Mgt Attention to Program Warranted ML20248E2351989-09-27027 September 1989 Forwards Summary of Issues Re Verification of Quality of Certain Types of Activities Performed for Mods at Facility. Mods Cover Automatic Depressurization Sys/Msiv Instrument Nitrogen Accumulator & Svc Water Pipe Replacement ML20248A4111989-09-25025 September 1989 Forwards Restart Team Safety Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted ML20248E5581989-09-21021 September 1989 Forwards SER Supporting Use of Frosstey Fuel Performance Code Described in Topical Rept PECo-FMS-003, Steady-State Fuel Performance Methods Rept. Addl Applications of Subj Code Require NRC Review & Approval ML20247L9331989-09-13013 September 1989 Advises That Written Reactor Operator Licensing Exams Scheduled on 891211 & Operating Exams on 891212-15.Ref Matl Listed on Encl Should Be Provided by 891001.Simulator Exam Scenario Should Be Retained Until Exam Process Completed ML20247E8491989-09-0707 September 1989 Forwards SALP Board Repts 50-277/88-99 & 50-278/88-99 for Aug 1988 - June 1989 ML20247B8711989-09-0101 September 1989 Forwards Restart Safety Insp Repts 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted ML20246E0241989-08-21021 August 1989 Forwards Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Re Components Required to Trip Reactor & Interface W/Nmss Vendors or Vendors of Each Component,Respectively ML20246J4571989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20 ML20248D0261989-08-0101 August 1989 Confirms 890714 Telcon & Requests Assistance & Cooperation in Review of Allegation Involving Plant.Util Should Fully Review Allegation & Take Action in Accordance W/Encl Instructions.Encl Withheld (Ref 10CFR2.790) ML20248C0421989-07-28028 July 1989 Responds to Util in Response to NRC Re Potential Violation of 10CFR50.7.Review of Record Indicates That Violation May Have Occurred.No Further Action Warranted as Case Settled Prior to Investigation ML20247E3191989-07-21021 July 1989 Relaxes Requirements of Section V.A of 870331 Order to Permit Operation of Unit 2 to Full Power ML20246F6121989-07-0606 July 1989 Forwards NRR to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Petition Being Treated Under 10CFR2.206 ML20246C3681989-06-30030 June 1989 Forwards Safety Evaluation Supporting 871019 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability, On-Line Testing of Reactor Trip Sys. Existing Test Intervals Consistent W/High Reactor Trip Sys Availability ML20246B9561989-06-28028 June 1989 Forwards Annual Emergency Preparedness Exercise Safety Insp Repts 50-277/89-17 & 50-278/89-17 on 890614.No Violations Noted ML20246B9161989-06-28028 June 1989 Advises That Requirements of 870331 Order Relaxed to Permit Unit 2 Operation Not to Exceed 70% Full Power,In Accordance W/Section Ve of Order ML20246A0001989-06-26026 June 1989 Forwards Restart Safety Insp Repts 50-277/89-16 & 50-278/89-16 on 890507-0617 & Notice of Violation ML20245C9671989-06-16016 June 1989 Requests Addl Info on Response to Generic Ltr 88-01 on IGSCC in Matls.Response Should Be Provided within 60 Days of Receipt of Ltr ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247N8481989-05-25025 May 1989 Forwards Safety Insp Repts 50-277/89-12 & 50-278/89-12 on 890410-13.No Violations Noted ML20247L6481989-05-24024 May 1989 Forwards Restart Safety Insp Repts 50-277/89-15 & 50-278/89-15 on 890402-0506.No Violations Noted.Two Issues Remain Unresolved,Including HPCI Sys Wiring Error That Occurred During Plant Mod Installed in Mar & Apr 1989 ML20247K9191989-05-18018 May 1989 Forwards Electrical Insp Repts 50-277/89-13 & 50-278/89-13 on 890405-07 & 13.Issues to Be Resolved Before Unit 3 Restart Listed.No Violations Noted ML20246N3401989-05-10010 May 1989 Advises That Written Senior Reactor Operator Licensing Exams Scheduled for 890814 & Operating Exams Scheduled for Wk of 890918.Ref Matls Listed on Encl Should Be Provided by 890601 ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20245J0821989-04-26026 April 1989 Modifies Requirements Set Forth in 870331 Order,Section V.A to Permit Operation of Unit 2 Not to Exceed 35% Full Power ML20245F3181989-04-26026 April 1989 Requests Encl Addl Info Re Util 890310 Application for Amends to Licenses DPR-44 & DPR-56 Re Intermediate Detector Not in Startup Position for Calibr 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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) 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 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 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 ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K2251999-06-11011 June 1999 Forwards Insp Repts 50-277/99-04 & 50-278/99-04 on 990405- 0517.One Severity Level IV Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207G2051999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20207B8381999-05-24024 May 1999 Forwards FEMA Final Exercise Rept for Peach Bottom Atomic Power Station Plume Exposure Pathway Exercise Conducted on 981117.One Deficiency & 27 Areas Requiring Corrective Actions Identified ML20207A0541999-05-17017 May 1999 Acks 990512 & 14 Telcons with Licensee Re Util Request That Rev 8 of NUREG-1021, OL Exam Stds for Power Reactors Be Followed Rather than Interim Rev 8 for Exams in Sept 1999. Request Acceptable ML20206K2231999-05-0606 May 1999 Informs That Author Authorized to Exercise Discretion & Not Issue NOV or Civil Penalty Re Violation Util Identified Involving Unit 2 Rod Block Monitoring Sys Being Inoperable for 29 of 185 Control Rods ML20206K1921999-05-0606 May 1999 Discusses 990503 Telcon Between J Williams & B Bierly Re Arrangements Made for Administration of Licensing Exam at Peach Bottom Facility During Week of 990913 ML20206A1511999-04-20020 April 1999 Forwards Request for Addl Info Re Util 980514 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-operated Valves. Response Requested within 90 Days of Ltr Receipt ML20206A2801999-04-20020 April 1999 Discusses Proposed Changes Submitted by PECO on 980416, 981116,990122 & 990211 to Plant Emergency Action Levels (Eals).Eals Incorporate Guidance in NUMARC/NESP-007,Rev 2. SE Supporting Proposed EALs Encl ML20205N1961999-04-0909 April 1999 Informs of NRC Planned Insp Effort Resulting from Peach Bottom Atomic Power Station Plant Performance Review Conducted for Period April 1998 to 990115.Historical Listing of Plant Issues & Insp Plans Through Jan 2000 Encl ML20205K7321999-04-0707 April 1999 Forwards Amends 227 & 230 to FOLs DPR-44 & DPR-56, Respectively.Amends Consist of Changes to TS SRs Re Secondary Containment Doors,In Response to 980204 Application,As Revised by ML20205J0531999-04-0101 April 1999 Ack Receipt of 990326 Notice of Enforcement Discretion Request & Documents Resolution.Notes That E3 EDG Returned to Operable Status on 990327,within 14 Day Completion Time Required by Ts.No Enforcement Discretion Necessary ML20205B9891999-03-25025 March 1999 Forwards Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.Violation Noted & Being Treated as non-cited Violation.Nrc Concluded That Staff Maintained Effective Influents Controls & Effective Security Program ML20203H8101999-02-12012 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, ML20203H7751999-02-12012 February 1999 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom Atomic Power Station ML20202J5251999-02-0101 February 1999 Forwards Insp Repts 50-277/98-11 & 50-278/98-11 on 981110- 990104 & Notice of Violation Re Failure to Complete Facility Licensed Operator Requalification Program ML20202J8081999-02-0101 February 1999 Forwards Insp Repts 50-277/98-09 & 50-278/98-09 & Notice of Violation.Insp Focused on Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operation Conditions ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20198P1761998-12-30030 December 1998 Forwards from R Calvan Transmitting FEMA Rept for Spring 1998 Peach Bottom Atomic Power Station Ingestion Exposure Pathway Exercise.No Deficiencies Identified During Exercise Conducted on 980407-09,980506 & 980519-21 ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls IR 05000277/19980081998-12-21021 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-277/98-08 & 50-278/98-08 Issued on 981028 ML20198D4071998-12-16016 December 1998 Forwards Emergency Preparedness Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Exercise Weaknesses,Safety Concerns or Violations of NRC Requirements Identified 1999-09-07
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DEC 0 9 IW Docket Nos. 50-277 50-278 Philadelphia Electric Company ATTN: Mr. J. W. Gallagher Vice President Nuclear Operations 2301 Market. Street-Philadelphia, Pennsylvania 19101 Gentlemen:
Subject: Inspection No. 50-277-86-25 This refers:to your letter dated September 25, 1987, in response to our' letter dated July 22, 1987.
-Your letter provided. additional information on four items fc,r which we requested clarification in our July 22, 1987 (W. V.' Johnston, NRC_to J. W. Gallagher, PECo) letter. We find the information to be responsive to our
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request.
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Thank you for informing us of the corrective and preventive- actions documented -
in your letter. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely, 0.,L;,121;icu,1ry:
William V. Johnston, Acting Director Division of Reactor Safety cc w/ enc 1:
Dickinson M. Smith, Manager, Peach Bottom Atomic Power Station John S. Kemper, Senior Vice President, Engineering and Production
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-Thomas S. Shaw, Jr., Vice President, Production Troy B. Conner, Jr. , Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric
. Rm G.'Leitch, Nuclear Generation Manager yg Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)
Raymond L. Hovis,. Esquire r e4o
$$mo Thomas Magette, Power Plant Siting, Nuclear Evaluations W. M. Alden, Engineer in Charge, Licensing Section-mz Doris Poulsen, Secretary of Harford County Council
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' Public Document Room (PDR)
Local Public Document Room (LPDR)
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RL LIM 1 86-25 - 0001.0.0
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OFFICIAL RECORD COPY t w__________
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Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
Section Chief, DRP j Robert J. Bores', DRSS
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699
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PHILADELPHIA PA.19101 (215) 841 5020 M. J COONEY
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'.".. .. . .,, September 25, 1987 Docket Nos. 50-277 50-278 Mr. William V. Johnston, Acting Director Division of Reactor Safety-Region I U. S. Nuclear _ Regulatory Commission ATTN: Document Control Desk-Washington, D. C. 20555 SUBJECT: Additional.Information in Response to
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Inspection Report No. 50-277/86-25 for Peach Bottom Atomic Power Station REFERENCES: 1) Letter from W. V. Johnston, NRC, to J. W. Gallagher, PECO, dated July 22, 1987.
2) Letter from J. W. Gallagher, PECo, to W. V. Johnston, NRC, dated April 24, 1987.
Dear Mr. Johnston:
This is in response to your letter (Reference 1) which requested clarification of four items in our response (Reference 2) to Inspection Report No. 50-277/86-25. The NRC was informed that an extension to the due date would be needed to complete preparation of this response. Your requests are restated herein followed by our response.
. Fire Watch Requirements For Weekly Diesel Generator Test NRC Request:
In response to the Notice of Violation, your corrective actions are not clear as.to whether you will permit the plant operator performing the weekly diesel generator full load test to satisfy your fire watch requirement if the Cardox system'is defeated, or whether an individual with no other If the job related duties other than a fire watch will be used.
former'is the case, please provide your justification.
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Mr. William September 25, 1987 Page 2
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Response
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The plant operator is not permitted to satisfy the diesel fire watch requirements because he has duties other than fire watch duties to perform while in the room. However, a fire watch is not required during the weekly test because.the Cardox system is defeated for only a short period of time (less than 15 minutes). If the automatic injection mode of the Cardox is defeated for more than a nominal 15 minutes, steps will be taken to establish a dedicated fire watch (someone other than the operator). The fire watch would be in place within one hour from the time the Cardox was defeated to satisfy Technical Specification 3.14.B.4, unless the automatic Cardox protection is restored in that time period. Defeating the Cardox system only inhibits the automatic injection feature for that room and does not disable the diesel room alarm system (red revolving beacon and horn). A dedicated fire. watch is not necessary while the-operator is located in the diesel room with the Cardox system defeated since the operator's observations and the alarm system could alert the operator to a fire, in which case he would rearm the system.
To perform the weekly diesel generator test the operator enters the diesel room and performs the prestart line-up and checks with the automatic injection mode of the Cardox defeated. This normally takes less than 15 minutes. A local red light indicates to the operator the defeated status of the automatic injection mode of the Cardox. Once the. diesel generator has been started, the operator rearms the Cardox and leaves the room. The operator does not remain in the room for more than a few minutes while the diesel generator is operating due to the loud noise and the heat. The operator does reenter the room at some point during the test, defeat the automatic injection mode of the Cardox and record data required for the test. This also should take less than 15 minutes. Upon completion the operator rearms the Cardox and leaves the room.
The procedure for starting the diesel generators (S.8.4.A) and the weekly test procedure (ST 8.1) require the operator to always rearm the Cardox when leaving the room, and to request shift supervision's permission to keep the automatic injection mode of the Cardox defeated for more than 15 minutes. If shift supervision approves, they will take steps to establish a fire watch within the next 45 minutes. The fire watch will be a person with no duties other than fire watch duties.
Defective DC Bus Low Voltage Alarm Relay NRC Request:
In response to the Notice of Deviation, you indicated that as of April 14, 1987, you were in full compliance with your FSAR commitments regarding testing of the relays. During the testing you had done, as witnessed by the inspector, one relay performed unsatisfactorily in the non-conservative direction.
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Mr.. William September 25, 1987 Page 3
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l You'also indicated'that this relay will be replaced with~a new L relay.which is on order. Please describe any compensatory l actions you may have taken as a result of the unsatisfactory performance until the relay is replaced and indicate the expected completion of the relay replacement.
Response:
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A replacement relay has been received from the
! manufacturer; however, upon inspection it was determined that it l is notLidentical in design to the failed relay. Therefore, its installation will be implemented as a modification. The replacement will be completed by October 31,.1987.
Compensatory actions are not currently considered l necessary because:
1. The failed relay monitors DC voltage at the 20D12 250 vde bus which is~ powered by two battery chargers.when AC power is available and by two 125 vde batteries during loss of AC power. The voltage at-the output of each of those batteries is monitored by low voltage .
alarm relays which also annunciate in the control room. The 20D07'250vde bus is also powered by these two batteries and is equipped with a low voltage control room alarm relay which was tested satisfactorily on January 29, 1987. These other alarm features provide an important measure of compensation for the failed alarm relay. Attached is a figure presenting the configuration of this system.
2. A weekly surveillance test monitors the battery voltage, and battery charger voltage is checked daily.
3. The 250 vde bus with the failed relay provides electric power to only one system (RCIC on Unit 2),
which is required to be operational only during power operation. Presently Unit 2 is shutdown and the failed alarm relay will be replaced prior to startup.
l 4. The batteries were replace,d in 1985 with new l batteries.
Schedule For Emergency Operating Procedure Revisions NRC Recuest:
In your response to the area of weakness regarding emergency operating procedures, you have deferred the completion date of activities beyond our understanding at the conclusion of the exit. It was our understanding that a revision to the emergency. operating procedures would be made in August 1987.
Your response leads one to conclude that these revisions are expected to be completed as late as June 1988 with operator
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Mr. William September 25, 1987 Page 4 i
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training in these procedures to be completed as late as December 1988. Please explain the delay in the completion of the revision and training in emergency operating procedures.
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Response:
The dates provided in our response for completion of the containment venting and blackout procedure revisions were established by station management with the understanding that no schedular commitments regarding these two procedures were made during the inspection. We regret this apparent misunderstanding.
We concentrated our efforts on incorporating Revision 3 of the BWR Owners Group Emergency Procedure Guidelines into the Peach Bottom TRIP Procedures. Associated procedure revisions were approved in August, 1987 and operator training has been completed. Completion of this project has permitted us to focus more attention on revising the containment venting and blackout procedures. Revision of the containment venting procedure has i
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been rescheduled for completion by November 30, 1987 and the blackout procedure by January 31, 1988. Operator training on each of these procedures will be completed within one licensed operator requalification training cycle following procedure approval (less than 4 months).
Preventive Maintenance on Diesel and Switch Gear Room Fans NRC Request:
Finally, we request you clarify your response regarding the weakness in maintenance and testing support equipment. In your response regarding maintenance on the diesel generator and switch gear room fans, you indicated that the fans were included in the preventive maintenance program but that maintenance has not been performed in accordance with the program schedule and that accessing some of these fans may impact operability of safety related systems. Furthermore, your response implies that no preventive maintenance will be performed on this equipment until at least next year while you determine the means to perform such preventive maintenance tasks. We consider that deferral of preventive maintenance on these fans may also affect operability of safety related systems. Please provide information to support your proposition that deferring preventive maintenance until next year is an acceptable approach.
Response:
We acknowledge that our response did imply that no preventive maintenance would be performed on the fans until next year; however, that was not our intention. At the time, we t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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Mr. William September 25, 19 B'
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intended to do as much of the preventive maintenance (PM) on these fans as possible within the next few months. We l anticipated, however, that we may complete some of the PM aftez the end of the year. ,'
Since the inspection of December 8-19, 1986 e considerable progress has been made in this area. Vibration monitoring has been performed on one of the Battery Room Exhaust Fans (OBV-36) and all of the and Diesel Generator Room Supply Fans (OAV-64, OBV-64, OCV-64 and ODV-64). Couplings on both of the Battery Room Exhaust Fans and one of the Diesel Generator Room Supply Fans (ODV-64) have been lubricated. The motor on one of the Diesel Generator Room Supplemental Supply Fans (ODV-91) !
has been disassembled, inspected, and reconditioned. As part of
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the reconditioning, an electrical megger test was performed, and the shaft and bearings were inspected. This motor was found t'o be in excellent condition.
The remaining PM to be performed on the Dieset ,
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Generator Room Supply Fans (OAV-64, OBV-64, OCV-64 and ODV-64) h.
consists of an electrical megger test on each motor and coupling lubrication on the OAV-64, OBV-64 and OCV-64 fans. This work is scheduled to be completed during the annual diesel generator inspections which are in progress and scheduled to be completed in October 1987.
The remaining PM to be performed on the Battery Room Exhaust Fans (OAV-36 and OBV-36) consists of an electrical megger test of both fan motors, and vibration monitoring on the OAV-36 fan. The electrical megger test of the OBV-36 fan motor will be ,e d done this year. The OAV-36 fan is presently out of service for ';
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corrective maintenance. The remaining PM on this fan will be performed in conjunction with the corrective maintenance ,'
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activity. Vibration data will be taken after this motor is ! ;
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returned to service.
Vibration monitoring of the Diesel Generator Room ( g Supply Fans and Battery Room Exhaust Fans will continue '
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periodically under a Predictive Maintenance Program. f I f
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In January 1988, another one of the Diesel Generator Room Supplemental Supply Fan motors will be disassembled, inspected and reconditioned. If the motor is found to be in ,
excellent condition (similar to the ODV-91 motor) then another '
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motor will be inspected in January 1989, and the last motor will ,
be inspected in January 1990. If the results of a motor inspection reveal abnormal degradation, the schedule for I inspection of the remaining motor (s) will be accelerated as 'I appropriate. Inspection and reconditioning will remain as the ,1,f 1 designated PM on the Diesel Generator Room Supplemental Supply 1 Fan motors until completion of a modification to facilitate /
vibration monitoring. After the modification is completed, vibration monitoring and electrical megger tests of these fan motors will be scheduled accordingly in lieu of disassembly, inspection and reconditioning.
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