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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 STATE/LOCAL GOVERNMENT
MONTHYEARML20245F0021989-06-20020 June 1989 Responds to Re Adequacy of Licensee Resources to Operate Plant W/O Undue Reliance on Overtime During Operator Licensing Exam ML20247E3431989-03-29029 March 1989 Discusses 890227 Submittal Re Agreement Between Commonwealth of PA & Util Concerning Plant.Concerns Raised That Some Agreements Inconsistent W/Nrc Regulations.Meeting to Resolve Inconsistencies Suggested ML20196A1851988-11-30030 November 1988 Responds to Appeal of Denial of FOIA Request for Documents. Forwards Portions of Elsasser 880505 Memo.Marcus 871222 Memo Withheld (Ref FOIA Exemption 5) ML20195H6971988-11-22022 November 1988 Documents Substance of 881116 Discussion Following Pennsylvania Senate Committee Hearing.Discussed Possible Methods Available to Incorporate Into NRC Requirements Contemplated Agreement Between Commonwealth & Util ML20196C6471988-11-10010 November 1988 Informs That Commissioners Will Be Unable to Attend 881116 Hearing Re Plant Restart,Per 881026 Request ML20154J4881988-09-16016 September 1988 Responds to 880816 & 0913 Ltrs Re NRC Recent Decision to Impose Civil Penalties on Util & Util Employees & Manner in Which Commission Exercised Regulatory Oversight Responsibility for Facility ML20151G9821988-06-16016 June 1988 Ack Receipt of Comments on Util Plan for Restart of Plant. Comments Will Be Factored Into Review of Util Plan ML20151D0221988-04-0707 April 1988 Responds to Raising Number of Concerns Re Plant. Decision to Permit Restart Will Not Be Made Until Commission Convinced That Previous Problems Corrected & That Operation of Facility in Safe Manner Assured ML20153E6341988-04-0606 April 1988 Responds to Supporting Petitions Submitted by Commonwealth of PA Requesting Hearing Prior to Restart of Plant.Commission Has Concluded That Discretionary,Formal Adjudicatory Proceedings Unnecessary ML20147G6601988-02-29029 February 1988 Responds to Expressing Concerns Re Potential Failure of Containment in Event of Severe Accident.Nrc Sponsored Research Indicate Some Low Probability Severe Accident Sequences.Methods for Improvements Being Pursued ML20147H5871988-02-29029 February 1988 Responds to Re Concerns of Potential for Failure of Containment in Event of Severe Accident & Deficiencies in Mgt.Probability of Containment Failure Very Low.Mgt Control Problems Discussed W/Util on 880226 ML20195J3921988-01-13013 January 1988 Informs That 871120 Petition for Hearing on Util Untimely & Does Not Address Commission Criteria in 10CFR2.714(a),(d), 2.714(a)(1) & 2.772(c).Petition Rejected ML20236X4391987-12-0707 December 1987 Ack Receipt of Resolution 39-87 Requesting That NRC Deny Authorization to Restart Plant Until Util Submits Detailed & Comprehensive Plan & Schedule to Assure That Facility Will Be Operated Safely ML20236V7341987-12-0101 December 1987 Partial Response to FOIA Request for Documents.Forwards Documents Listed in App C ML20236R4091987-11-19019 November 1987 Ack Receipt of Review & Comments on Util Commitment to Excellence Action Plan Submitted Per NRC Order Shutting Down Plant on 870331.Comments Forwarded to Util for Consideration in Revising Plan ML20149F8581987-11-17017 November 1987 Responds to Comments Re Util Commitment to Excellence Action Plan,Submitted in Response to NRC 870331 Shutdown Order. Comments Forwarded to Util for Use in Revised Plan.Staff Level Meeting Planned Near Site ML20238B2991987-08-24024 August 1987 Responds to Expressing Concern That Mgt & Safety Problems Recently Identified at Facility Could Endanger Constituents.Nrc Ready to Take Appropriate Action If Performance Degrades to Levels Endangering Public ML20235P4011987-07-13013 July 1987 Responds to Addressing Concerns W/Nrc Response to Recent Events at Plant.Plant Shut Down Due to Problem of Sleeping Operators.Industry Alerted by Incident & Measures to Assure Alertness of Operators Taken ML20214L0211987-05-26026 May 1987 Advises of 870623 Meeting W/Harford County Board of Health to Discuss Current Status of Activities at Plant & Mark I Containment Issue Referred to in Recipient .Nrc Will Be Able to Respond to Questions Re Actions at Plant 1989-06-20
[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
[Table view] |
Text
[ Distribution:
Docket File TMartin e
' fp uog'o UNITED STATES NRC PDR FGillespie i
'g Local PDR DMossburg l
! o . NUCLEAR REGULATORY COMMISSION 3 i WASHINGTON, D. C. 20555 E00 3508 !
o f TMurley/JSniezek l FMiraglia j
%,*****/ April 7, 1988 SVarga j CHAIRMAN 880ggr :
l WButler REMartin/RClark U Brien I NRR Mailroom PDI-2 Reading i 0GC )
The Honorable William Donald Schaefer Stello Governor of Maryland r Annapolis, Maryland 21401 fae ussell, RI
Dear Governor Schaefer:
I am responding to your letter of February 12, 1988, in which you raised a number of concerns regarding the Pa=rh R 3 t t om A t onia:
Power Station. Specifically, you questioned whetler the Commission had adequately defined the problems at Peach Bottom and l whether we have 2eveloped suitable criteria to assess the readi- j ness of the plant to resume operations. J In the Commission's view, the problem at Peach Bottom is wel? I defined. The NRC shutdown order, our reports on routine inspec- l 4 t'ons, and the Systematic Evaluation of Licensee Performance I (SALP) reports all define waaknesses that must be corrected before a decision on restart can be made. The solutions proposed to correct those weaknesses must demonstrate that Philadelphia _ i Electric Company (PECo) is fully capable of opera, ting Peach Bottom within the confines o' the Commission's safety requirements befor' any Commission decision can be made to allow restart of the ,
facility. !
It is important to recognize that it is the responsibility of PEco, not NRC, to formulate programs that address the weaknesses ;
that have been identified at the plant. In partici!1ar, PECo must l demonstrate that it has provided strengthened line management to -
)
ensure safe opera' ion of the facility, strong independent over- l sight of operating activities to ensure that problems are quickly identified and effectively corrected, and an operating environment that fostr- safe, professional operation of the facility, i PECo's fi.. recovery plan did not satisfy NRC's concrirns. In response to our finding, PECo provided additional, revised ,
material in November 1987 and February 1988. We are still !
evaluating these submittals. You have already provided us with !
your comments on the licensee's earlier action plan, and we will l be pleased to consider any further comments you may have on their !
revised plan.
l 1
3 $,)o Origiaated: NRR: Martin
~ A 6 / I:
8804130356 000407 C PDR ADOCK 05000171 p3 ,N eg D('
U PDR 1
!o
\ .
i ,
2 When a facility such as Peach Bottom is shut down for safety reasons, the NRC does have in mind specific corrective actions i
that must be satisfactorily implemented before the plant can be i permitted to restart. Substantial changes are needed in per- ;
sonnel, organizational interactions, and procedural implementation ,
at all levels of the PECo organization. PECo's recovery plan is the blueprint for the needed change. Once accepted by the NRC as a satisfactory plan of action to bring about the needed change at Peach Bottom, fulfillment of the requirements of this plan become the essential "restart criteria" that you are requesting. The NRC uses the utility recovery plan as a basis when evaluating restart readiness. The NRC staff determines the effectiveness of the recovery plan's implementation and whether it is having the
,esired effect in correcting the problems you have described in
. your letter, j i
Underlying the problems at Peach Bottom is the attitude problem l that existed from the corporate level to the control room. PEco has the responsibility to address this problem, and we expect this- l will be PECo's most difficult challenge. The Commission has !
already expressed its views on this matter at the public meeting i on September 14, 1987, when PECo presented its initial recovery '
plan to the Commission. The recent appointment of a new Chief Executive Of ficer and Executive Vice President, both with nuclear ,
utility backgrounds, should make a major contribution to bringing j about the changes that are necessary before the Commission will !
allow restart of Peach Bottom.
f However, there are no laws, regulations, or other standards that address individual attitudes. Attitudinal problems do not lend themselves to measures of performance based on objective j standards. The NRC must have confidence, based on direct 1 j observation of licensee performance at every level of the !
, organization, that management and supervision both at the I corporate of fice and at the f acility are commi tted to, and require, high standards of professional performance from its employees. Over the next several months as our inspectors, technical reviewers, managers, and the Commission itself continue to interact with representatives of PECo, we will not only evaluate the plant hardware and procedures, but also the in-dividuals with whom the safe operation of the facility may once again be entrusted. !
We also share your concern about the issues raised in the recent letter from Mr. Zack Pate of the Institute of Nuclear Power Operations (INPO) to the PECo Board of Directors. We note that Mr. Pate's concerns involving poor performance at Peach Bottom I l
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encompass a number of issues which have already been identified and are being reviewed by the NRC. As an example, improper actions by operators which led to the shutdown have been the basis of ongoing NRC enforcement conferences with the involved licensed operators and their former supervisors. In our deliberations, we will insure that PECo addresses each of the issues raised by Mr.
Pate prior to any decision on restart of Peach Bottom.
Ultimately the Commission will decide whether the Peach Bottom plant will be allowed to restart. We will make that decision based on a careful review of the licensee's recovery plan and the staff's evaluation of its implementation. Prior to reaching any decision on restart, the Commission will be briefed by the staff in a public meeting. Based on that briefing, the Commission will make its decision with respect to restart of Peach Bottom. I can assure you that a decision to permit restart will not be made until the Commission is convinced that previous problems have been corrected and that there is reasonable assurance that PEco can operate the facility in a safe manner and in accordance with applicable NRC regulations.
Please be assured that we will continue to take into account the concerns of the State of Maryland with respect to the restart process at Peach Bottom.
Sincerely.
-de OJ. W N*
Lando W. Zeo,, Jr
i, UNITED STATES NUCLEAR REGULATORY COMMISSION O :j WASHINGTON, D. C. 20555
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I g$h![I[f Enri PRINCIPAL CORRFSPONDENCE CONTROL l
FROM: Dt E: FDri r.ONTROL: 007508 7, ._j
,7% 7M nrir DT: o?/12/83 WILLI AM DONAl D TCHAFFFR / gjfp FINAL RFPLY:
GOV. OF MARYLAND
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TO:
CHAIRMAN 7ECH FOR SIGNATIIRF OF: ** PRIORITY *+ SFCY NO: RR-119 CHAIRMAN ZECH DESC: ROIITINO:
QUESTIONS CONCERNINii SAFF OPERATION OF PEACH STELLO BOTTOM T AYl.OR
_ __ RFHM eDATE: 02/1R/8A Ri l:.*:41 L . RI NRR CONTACT: MitRIEY Mi tRR AY , OGC (ASSIGNEDTri 3 5SPECIAL INRTRUCTIONS OR RFMARMS:
0 NRR RECEIVED: FEBRUARY 19, 1988 ACTION: -- DRPR:VARGA .,
NRR ROUTING: MURLEY/SNIEZEK MIRAGLIA MARTIN GILLESPIE tOSSBURG
r . ;
OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET 3 PAPER NUMBER: CRC-88-0119 LOGGING DATE: Feb 17 88 I t
ACTION OFFICE: EDO f l
AUTHOR: W.D. Schaefer i AFFILIATION: MD, GOVERNOR LETTER DATE: Feb 12 88 FILE CODE: ID&R-5 Peach Bottom
SUBJECT:
Tssues surrounding Peach Bottom ACTION: Signature of Chairman DISTRIBUTION: RF, GPA/SLITP to Ack SPECIAL HANDLING: None NOTES:
DATE DUE: Feb 29 88 ,
t SIGNATURE: . DATE SIGNED:
AFFILIATION: l
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OFFICE OF THE GOVERNOR IN REPW RUER To G.g4 wu.u w Do u u a
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suinoet o s<t February 12, 1988 e w asr ,,rstoTs't,'r'rl astuostu g g,rg us Notogagt Mr. Lando W. Zech, Jr., Chairman *** No'g/gfgjig Nuclear Rcquiatory Commission ac2: oa ms 1717 H Street, N.W. voo my in >3e Washington, D.C. 20555
Dear Chairman Zech:
As you know, members of your staff briefed me and members of the Maryland Congressional Delegation last week on the issues surrounding the Peach Bottom Nuclear power plant.
I am, quite frankly, more concerned now about the situation at Peach Bottom than I was before the briefing.
I am sure you agree with me that we have an obligation to protect the public safety. More than any other form or energy, nuclear power requires absolute public confidence. The consequences of a mistake are too great.
Although we maintain a careful review of the power plants in and around the state, Maryland has no formal standing t
. in the review process. Ultimate responsibility for the safe operations of Peach Bottom, as with any nuclear power plant, rests with the NRC.
What troubled me most was not what I heard but what was missing from the briefing. I had hoped to hear your plans for ensuring that the long-standing problems at Peach Bottom would be corrected prior to restart. What I heard instead were vague categories, not a specific plan of action.
Determining what restart criteria to use in judging
_w hether or not_Pjach Bottom can resume operat_i_ols__is.
Jerital and was not adequately addressec. Categories like "acceptable maintenance backlog" or "effective quality assurance program" cannot substitute for specific criteria. How will you know if a quality assurance 3
program is effective? What is an acceptable maintenance backlog? These are questions, like so many others, that must be answered now. How can I, as Governor, tell the people of Maryland that we are on the right track at Peach Bottom if we can't even define the problem, if we don't have a good yardstick by which to measure Peach Bott A rmance2_-- -
{y)[)DO N A sr ~
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Mr. Lando W. Zech, Jr., Chairman February 12, 1988 Page Two i
I What is most disappointing is the lack of direction in correcting the personnel problems that are at the root of A all Peach Bottom's dilficultie ]s. There is a perYagive attitude problem that runs trom tne contY31~ room at Peach BottTm~to'the boiird room at Philadelphia Electric. If there was any doubt as to just how pervasive this attitude problem is, those doubts were dispelled with the release of the recent letter from Zach Pate of the Institute of Nuclear Power Operations (INPO) to the PECO board of directors.
Much of the information in this letter leads me to believe that the plant should have been closed sooner.
But if the NRC was not aware that the personnel probrems throughout~PECO had deteri~otated to the, point where c~65tinued~ operation _of_the_ plant _was literally a threat-to the~ health and safety of the public, how will.
you know when this attitude problenjias been cor~recEed?
I am shocXEd Ey thW acti~ons and statements of the highest i officers of the corporation as documented in Mr. Pate's letter. It has been suggested that rehabilitation of the licensed operators is not possible. Frankly, I believe that changing the attitudee of operators will be easier than changing the attitudes of some corporate officers.
You must determine how to correct the'at~tl~tude problem, and verify that the corrections are effective. Simple assurances are not enough.
The NRC should identify specific restart criteria, make them publicly available, give interested parties such as the State of Maryland the opportunity to comment on them, and finalize them prior to proceeding any further with its review of Peach Bottom. As a start towards identifying specific criteria PECO should be required to improve its scores in the NRC's SyEtsmatic Assessmeht 6f LTcensee_Eerformance. The improvements sh'6u1T~be quantff~Ied. The NRC's inspection program should also be used to evaluate improvements in
- performance. Inspections conducted liiinWthe shutdown
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have continued to identify numerous violations of NRC rules. The NRC should require PECO to meet
' 4 Lefiniti Ja_inspretioILgo_a_1s, such as completing a specific period prior To restart (for exarple 6 months) without being cited for a violation.
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r Mr. Lando W. Zech, Jr., Chairman February 12, 1988 Page Three Some of the most useful information for assessing PECO's performance has come from independent sources such as INPO. It is essential that such independent reviews continue to be performed. The role of these parties should be formalized as part of the review process. All subsequent PECO plans should be reviewed by and revised to the satisfaction of INPO before they are submitted to the NRC.
I cannot emphasize enough the importance of the recent INPO letter in identifying the unabated continuation of
- e. problem which we had been led to believe was at least in the process of being corrected. I am fully aware that it is unprecedented for this information to have been made public, but it is clearly crucial that it was. I am writing Zach Pate directly to urge that all INPO reports on Peach Bottom during the shutdown and for one year beyond the restart also be made public. I urge you to join ne in this reque_st.
Finally, I was very glad to hear Dr. Murley affirm that the NRC will involve the State of Maryland in its review as extensively as possible. This commitment is essential to me. I assure you that we are keenly interested in participating in this process, and will cooperate with you and your staff in every way possible.
I look forward to hearing from you in the near future.
Sincerely,
' ') N,
, , ' q .{ t . e . .t : ' A r f ! ' * * ~' -
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Governor cc: Maryland Congressional Delegation l
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