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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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a Oocket Nos. 50-277 N
'50-278 Philadelphia Electric Company ATTN: Mr. C. A. McNeill Executive Vice President-Nuclear Correspondence Control Desk P. O. Box 7520 Philadelphia, Pennsylvania 19101 Gentlemen:
J
SUBJECT:
DEFINITION OF " EXTREMITY" FOR PURPOSES OF SETTING OCCUPATIONAL EXPOSURE LIMITS The purpose of this memorandum is to clarify the NRC's position regardin the definition of " extremity" for purposes of setting occupational exposure imits.
NRC inspections have shown that a number of licensees are using a definition of "extremtty" that is contrary to the provisions of 10 CFR Part 20.101, " Radiation Dose ~ Standards for Individuals in Restricted Areas". This regulation specifies that ' extremity" dose limits apply to the " hands and foreams; feet and ankles."
Information provided in NRC Infomation Notice No. 8126. Part 3. Supplement No.1, has been misunderstood, and was not intended to change what is considered to be an extremity. This Infomation Notice discusses placement of personnel dosimeters for detemining whole body doses.
Because of this apparent misunderstanding, we plan no enforcement action if your procedures have incorporated this mistaderstanding. We have issued the
. enclosed memorandum to provide clarification on the intent of Infomation Notice No. 81-26, and what is considered to be an extremity. We request that you ensure your procedures incorporate the applicable dose limits of 10 CFR Part 20.
Your cooperation with us in this matter is appreciated. Please contact an if you have any concerns or questions regarding this matter.
Sincerely.
Onima! Signed By:
hteld R. BeNamy Ronald R. Bellamy, Chief Facilities Radiol Icel Safety and 89o9050156 8j g 77 Safguas Bra FDR ADOCK C FDC Division Of Radiation Safety and P Safeguards
Enclosure:
Memorandum from LeMoine J. Cunningham to Ronald R. Bellamy, et. al., dated June 22, 1989 g
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AUG 181989 cc w/ enc 1:
- John S. Kemper, Sr., Senior Vice President-Nuclear l' J. W. Gallagher, Vice President, Nuclear Services E. C. Kistner, Chairman, Nuclear Review Board
.Dickinson M. Smith, Vice President, Peach Bottom Atomic Power Station Jack Urban, General Manager, Fuels Department, Delmarva Power & Light Co.
l John F. Franz, Plant Manager, Peach Bottom Atomic Power Station Troy B. Conner, Jr., Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric Bryan W. Gorman, Manager , 5xternal Affairs' Eugene J. Bradley, Est ce, Assistant General Counsel (Without Report)
Raymond L. Hovis, Esqi,ise Thomas Magette, power Plant Siting, Nuclear Evaluations
.G. A. Hunger, Director, Licensing Section Doris Poulsen, Secretary of Harford County Council Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
Section Chief, DRP PAD (23) SALP and (2) Inspection Reports R. Martin, NRR M. Johnson, EDO J. Dyer, EDO F. Congel, NRR/DREP L. Cunningham, NRR/PRPB M. Knapp, DRSS f
RI:DRSS S RI:DRSS Wb I
erbini Pasciak Ballamy 7/2t>/89 y///89 j,7/v/89 "Efd!M.ECUPDCOM"
ENCLOSURE f S,, /f f =cg'c, ,
UNITED STATES G' j .- c ; g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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- A' ,' 6 j JUN 2 21989 MEMORANDUM FOR: Ronald R. Bellamy, Chief. EPRPB, DRSS, Region I Douglas M. Collins, Chief. EPRPB, DRSS, Region II L. Robert Greger, Chief, RPB, DRSS, Region 111 Blaine Murray, Chief, RPSB, DRSS, Region IV Gregory P. Yuhas, Chief. EPRPB, DRSS, Region Y FROM: LeMoine J. Cunningham, Chief Radiation Protection Branch Divisior of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
SUBJECT:
CORRECTION OF MISUNDERSTANDING CONCERNING OCCUPATIONAL DOSF LIMITS FOR " EXTREMITIES" The purpose of this memorandum is twofold: (1)todocumentthecorrectionofa misunderstuiding concerning occupational dose limits for " extremities," and (2) to provide guidance concerning potential enforcement action in cases in which licensees have incorporated this misunderstanding into their procedures.
10 CFR Part 20 provides different occupational dose limits for (1) the "whole body; head and trunk; active blood-forming organs; lens of eyes; or gonads;"
(2) the " hands and forearms; feet and ankles"; and (3) the " skin of the whole body. " As indicated in the instructions for NRC Form 5, " Current Occupational External Radiation Exposure," the dose to the'" hands ano forearms; feet and ankles" includes the dose to the skin of these body parts. The dose to the skin is assessed at a depth of 7 mg/cmr in tissue. Thus, the limit for the
" skin of the whole body" and the limit for the "whole body..." apply to all parts of the body except the " hands and foreams, feet and ankles."
The term " extremities" has often been used to designate the " hands and fore-arms; feet and ankles," although this term is not used in 10 CFR Part 20. The term " extremities" is used in the pending major revision of 10 CFR Part 20 where it has the different meaning of " hand, elbow, are below the elbow, foot, knee, and leg below the knee." However, this revised definition should not be used until the effective date of the major revision.
l CONTACT:
John D. Buchanan, NRR 492-10g7 TCE$ 3
Multiple Addressees M 22 29 IE Infortr6 tion Notice No. 81-26, Part 3, Supplement No.1. " Clarification of Placement of Personnel Monitoring Devices for External Radiation," was issued July 19,1982. That infonnation notice discusses placement of personnel
- l. dosimeters for determining whole body doses in situations where the principal source of radiation is from underfoot. That information notice indicates, and our position continues to be, that, in these situations, "a reasonable placement for a whole body dosimeter would be just above the knee." That information notice also notes that " extremity monitoring requirements may dictate the placement of additional dosimeters in the feet and ankle area.*
i Information notices cannot impose or change regulatory requirements and Infor-mation Notice No. 81-26, Part 3, Supplement 1 did not change the requirements of 10 CFR Section 20.101. Nevertheless, some licensees and, in at least one instance, regional personnel have maintained, incorrectly, that Information Notice No. 81-26, Part 3, Supplement I defined or redefined the terms
" extremity", or " extremities" to include the knee and the lower leg between the knee and the ankle and thereby extended the applicability of the 18.75 rem dose limit for the " extremities" to the lower leg above the ankle and to the knee.
Some licensees have changed their radiation protect!on procedures to incorpo-rate this misunderstanding and thereby to misrepresent the dose limits of 10 CFR Part 20.
This misunderstanding of the requirements of 10 CFR Part 20 has been identified primarily in relation to potential violations of the occupational dose lin.its resulting from radiation (xposures from hot particles on or near the skin. One example of this misunderstanding is the result of an informal survey taken by one licensee and reported to t:.e NRC. In that survey, ten nuclear power stations were contacteo and asked, "If one of your personnel had been exposed to a hot particle in the region of the body between the middle of the knee and ankle, would you identify the dose as being to the skin of the whole body or to the extremityP Four stations responded, correctly, that they would record the dose as the skin of the whole body. The other six stations said they would record the dose as being to the " skin of the extremity", thus indicating their misunderstandings of both 10 CFR Part 20 and Information Notice No. 81-26, Part 3, Supplement Ho 1.
In summary, for exposures of the knee and the lower leg above the ankle, the applicable occupational radiation dose limits of 10 CFR Sect. . 20.101 are:
(1) the whole body dose limit of 1.25 rem per quarter or 3 rem per quarter, and (2) the skin of the whole body limit of 7.5 rem per quarter.
This memorandun is being placed in the NRC Public Document Room and I encourage you to make it available to licensees.
Licensees who have incorporated the misunderstanding concerning "e::tremity" doses into their procedures should be asked to correct those procedures; however, oc enforcement action should be taken for such incorrect procedures if 1
i
' Fultiple Addressees JUN 2 21989 the licensee corrects the procedure (s). Enforcement action should be consid-ered for any licensee who, after being given a copy of this memorandum, refuses
. to correct a procedure that incorporates the misunderstanding of the dose limits of 10 CFR Part 20; however, please contact me before you initiate any such action.
This memorandum has been coordinated with the Office of Enforcement.
l Le ne J. unningham, ief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation i
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INDEX OPERATING REACTDRS Licensee BWR Pg. No. Sys. Pg. No.
Boston Edison Company DN 50-293 6 12 - 13'
.P11 grim 1
'GPU Nuclear Corporation DN 50-219 4 9 Oyster Creek-1 Philadelphia Electric DNs 50-277/50-278 -5 10 - 11
. Company Peach Bottom 2/3 Power Authority of the DN 50-333 .
1 3-4
' State of.New York James A. FitzPatrick Niagara _ Mohawk Power DNs 50-220/50-410 3 7-8
. Corporation Nine Mile Point 1/2
.-- Northeast Nuclear DN 50-245 2 5-6 Energy Company Millstone 1 Vermont Yankee Nuclear DN 50-271 7 14 - 15 Power Corporation. Vermont Yankee Pennsylvania Power & DN 50-387/50-388 20 38 - 39 Light Company Susquehanna 1/2 Philadelphia Electric DN 50-352/50-353 21' 40 Company Limerick 1/2
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INDEXE OPERATING kEACTORS Licensee PWR-Pg. No. Sys. Po. No.
-Baltimore Gas and DNs 50-317/50-318 9 18' 19 Electric Company Calvert Cliffs 1/2 Connecticut Yankee DN 50-213 10 20 - 21' Atomic Power Co. Haddam Neck'
. Consolidated Edison DN 50-247 12 24 Co. of New York Inc. Indian Point 2 Power Authority of the DN 50-286 13 25 - 26 State-of New York ' Indian Point 3 Duquesne' Light Company DNs 50-334/50-412 8 16 - 17 Beaver Valley 1/2 Maine Yankee Atomic DN 50-309 14 27 Power Company Maine Yankee General-Public Utilities. DN 50-289 17 33 34
- ( ~.. Nuclear Corporation TMI 1 General Public Utilities- DN 50-320 18 35 - 36 Nuclear Corporation TMI 2 Northeast Nuclear DN 50-336 15 29 - 30 Energy Company Millstone 2 Northeast Nuclear DN 50-423 25 53 Energy Company Millstone 3 Public Service Electric DN 50-272/50-311 16 31 - 32 and Gas Company Salem 1/2 Rochester Gas & Electric DN 50-244 11 22 Corporation Ginna Yankee Atomic Electric DN 50-29 19 37
' Company Yankee Atomic Long Island Lighting Co. DN 50-322 22 41 - 44 Shoreham Public Service of DN 50-443 23 45 - 50 New Hampshire Seabrook 1
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