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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20246F9781989-08-17017 August 1989 Responds to Requesting Environ Assessment Re Resumption of Operation at Plant ML20236A4171989-03-0101 March 1989 Responds to 881222 Request That NRC Include Town of Bourne within Plume Exposure Pathway Epz.Entire Town Defined to Be within Ingestion Exposure Pathway EPZ Since Risk from Exposure Expected to Be Negligible ML20196C4151988-12-0101 December 1988 Responds to 881031 Requests from Town of Plymouth & Commonwealth of Ma for Addl Meetings Re Plant Emergency Preparedness Issues ML20205H2951988-10-13013 October 1988 Confirms 881012 Request to Address Commission at 881014 Meeting Re Restart of Plant.Commission Allotted Time for Personal Appearance at Beginning of Meeting ML20205B8321988-10-13013 October 1988 Responds to Re Results of NRC Integrated Assessment Team Insp,Results of Recent SALP & Current Status of Emergency Planning at Plant.Confirms 881012 Request to Address Commission at 881014 Meeting ML20205B7941988-10-13013 October 1988 Responds to Re Results of NRC Integrated Assessment Team Insp,Results of Recent SALP & Current Status of Emergency Planning at Plant ML20205C1741988-10-0707 October 1988 Confirms 880928 Request to Address Commission During 881014 Meeting Re Proposed Restart of Facility.Any Restart Decision Will Be Based on Judgement of Adequacy of Plant,Mgt & Offsite Emergency Planning ML20205B8791988-10-0707 October 1988 Confirms 881005 Request to Address Commission Scheduled 881014 Meeting Re Proposed Restart of Plant ML20207M2481988-10-0707 October 1988 Responds to Re Proposed Restart of Plant.Decision Will Be Based on Adequacy of Plant,Mgt & Offsite Emergency Planning.Commission Will Consider NRC Evaluations & Recommendations Re Restart at 881014 Meeting ML20154R5881988-05-27027 May 1988 Informs That Commission Has Not Made Decision Re Resumption of Plant Operations & Will Not Proceed Until Issues Addressed Satisfactorily.Nrc Evaluation of Direct Torus Vent Sys Will Determine Need for Environ Assessment ML20154C1561988-05-0909 May 1988 Responds to 880322 Request for Facility Fsar.Fsar Will Be Delivered within 2 Wks to ML Butler at Recipient District Ofc in Pembroke,Ma,As Requested ML20150F7091988-03-29029 March 1988 Forwards Response to Expressing Concern Re Both Process NRC Adopted to Reach Decision on Restart of Plant & Possible Timing of That Decision.Nrc Taking Necessary Steps to Assure That Plant Will Not Restart Unless Licensee Ready ML20148Q3221988-01-25025 January 1988 Responds to Re Constituents Alleged Core Exposure at Plant.Plant Experienced Fuel Problems in 1970s,fission Product Releases Resulted from Cladding Problems & Core Exposure Incident Has Not Occurred ML20239A7021987-12-0303 December 1987 Responds to Urging NRC to Convene Formal & Comprehensive Hearing on Plant Restart.Planned Public Meetings & Addl Steps Taken to Ensure Full Public Participation in Restart Process Listed ML20236W4981987-11-24024 November 1987 Responds to Requesting That NRC Perform Environ Assessment of Mods Made to Plant Containment Structure Prior to Restart.Util Will Not Be Allowed to Place Direct Torus Vent Sys Into Svc Until NRC Evaluation Complete ML20236T9521987-11-20020 November 1987 Responds to Urging NRC to Convene Formal & Comprehensive Hearing on Restart of Facility.Commission Believes That Commitment to Comprehensive Public Participation in Restart Decision Has Been Demonstrated ML20236W4381987-11-20020 November 1987 Responds to Urging NRC to Convene Formal & Comprehensive Hearing on Restart of Facility.Public Meetings Planned Discussed.More Views Will Be Heard & Considered Through Planned Meetings than in Requested Formal Hearing ML20236W9301987-11-20020 November 1987 Responds to Urging NRC to Convene Formal Comprehensive Hearing on Restart of Facility.Nrc Will Hold Public Meetings Before Taking Position on Facility Restart NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design1987-08-25025 August 1987 Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design ML20245B2111987-05-21021 May 1987 Responds to Re Emergency Response Plan & Request Re Pending Petition Concerning Facility.Nrc Awaiting FEMA Results of self-initiated Review of Overall State of Emergency Preparedness Before Responding to Petition ML20206C3571987-04-20020 April 1987 Responds to Forwarding Concerns of Mc Ott Re Facility.Response to Mc Ott Encl ML20212M5001987-03-0404 March 1987 Responds to 870130 Note Forwarding H Shetterly Re Availability of NRC Matls in PDR & Lpdr.Replacement Copy of Insp Rept 50-293/82-20 Will Be Placed in Plant Lpdr ML20209E6291986-08-26026 August 1986 Responds to 860731 Request to Be Kept Informed of Proceedings Re Facilities ML20212N1381986-08-25025 August 1986 Responds to 860714 Concerns Re Problems at Plant & Recommendation That Safety Issues Be Resolved Before Plant Resumes Operation.Nrc Insp History & Util Activities Since 860412 Shutdown Discussed.Related Info Encl ML20206M6321986-08-13013 August 1986 Responds to 860701 Request for Info Re Radioactive Emissions at Plant.Encl 1 Provides Requested Info,Including Identity of Releases Exceeding Limits for Normal Operation.Licensee Semiannual Radioactive Effluent Release Repts Also Encl ML20244E0761986-07-15015 July 1986 Responds to Encl Re Safety of Operations at Facility.Salp Repts,Special Diagnostic Team Insp,Augmented Insp Team & Confirmatory Action Ltr 86-10 Demonstrate NRC Pursuit of Responsibilities in Protecting Public ML20204G1251986-07-15015 July 1986 Responds to Listed Questions in 860715 Request Re Safety Operations at Plant,Including NRC Actions Taken to Assure That Deficiencies Identified in SALP Rept Corrected IA-87-645, Responds to Encl Re Safety of Operations at Facility.Salp Repts,Special Diagnostic Team Insp,Augmented Insp Team & Confirmatory Action Ltr 86-10 Demonstrate NRC Pursuit of Responsibilities in Protecting Public1986-07-15015 July 1986 Responds to Encl Re Safety of Operations at Facility.Salp Repts,Special Diagnostic Team Insp,Augmented Insp Team & Confirmatory Action Ltr 86-10 Demonstrate NRC Pursuit of Responsibilities in Protecting Public ML20207E4271986-07-11011 July 1986 Forwards Commissioner Responses to Prehearing Questions for 860716 Hearing on Significance of Mgt Problems at Commercial Nuclear Facilities in Response to ML20140H8221984-04-18018 April 1984 Forwards Press Release 84-50 Re NRC Proposed Fine Against Util for Failure to Implement Adequate Radiological Controls During Maint ML20054E6111982-06-22022 June 1982 Responds to Re Ma Executive Ofc of Energy Resources Request to Use Civil Penalty Imposed on Util in Home Weatherization & Conservation Program.Commission Considering Review of Director Denial ML20054H8551982-06-0202 June 1982 Responds to to Nj Palladino Re Concerns About Facility Operation.Assignment of Resident Inspectors to Maintain Continuous 24-h Coverage Is Not Best Approach to Assure Adequate Protection of Public Health & Safety ML20054E8491982-05-25025 May 1982 Responds to 820503 Request for Addl Info Re Safety Concerns Expressed by Local Residents Concerning Facility ML20062J3251980-09-30030 September 1980 Discusses Emergency Planning Regulations,In Response to Re L Boyd Concerns.Fema Is Responsible for Adequacy of Emergency Preparedness in States & Communities Around Nuclear Plants NUREG-0474, Forwards NUREG-0474 Re Safety of Pressure Suppression Containment Sys,Per 780615 Request.Rept Covers All Pressure Suppression Containment Designs in Use in Us.W/O Encl1978-08-0101 August 1978 Forwards NUREG-0474 Re Safety of Pressure Suppression Containment Sys,Per 780615 Request.Rept Covers All Pressure Suppression Containment Designs in Use in Us.W/O Encl 1989-08-17
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3071999-06-15015 June 1999 Forwards Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Plant ML20195K3851999-06-11011 June 1999 Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing.Application Seeks Approval of Proposed Indirect Transfer of FOL for Plant ML20196K9921999-06-0404 June 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328.As Part of Reorganization,Division of Licensing Project Mgt Created ML20207E7351999-05-27027 May 1999 Responds to Requesting Reduction in IGSCC Insp Frequency Per GL 88-01 to Be Performed During Upcoming RFO 12.Forwards SE Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of H Water Chemistry ML20207B6341999-05-26026 May 1999 Informs That Licensee 990415 Submittal Re Financial Position of Entergy Intl Ltd,Llc Will Be Marked as Proprietary & Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20207B7391999-05-24024 May 1999 Forwards from Kc Goss of FEMA to Cl Miller Forwarding FEMA Analysis of Prompt Alert & Notification Sys for Pilgrim Nuclear Power Station.Based on Review,No Significant Problems Exist with Alert & Notification Sys ML20207B0701999-05-24024 May 1999 Responds to Sent to Ofc of Congressional Affairs Requesting Info on Concerns Raised by One Constituent,J Riel Re Y2K Compliance of Pilgrim NPP in Plymouth,Ma ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206U7501999-05-17017 May 1999 Forwards Insp Rept 50-293/99-02 on 990308-0418.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML20206M1891999-05-11011 May 1999 Forwards SE of 980826 Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Sys Piping for Plant ML20206E0551999-04-29029 April 1999 Discusses Bulletin 96-03 Issued on 960506 & Beco Responses ,970207,981230,990121 & 990309 for Pilgrim Npp. Determined That Actions Taken Should Minimize Potential for Clogging of ECCS Suction Strainers ML20206B3031999-04-20020 April 1999 Forwards Insp Rept 50-293/99-01 on 990125-0307.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy.Security Program Was Also Inspected ML20205Q9491999-04-0909 April 1999 Informs That on 990225 NRC Staff Completed PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205B9391999-03-24024 March 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves ML20204C7871999-03-17017 March 1999 Informs That Application Submitting Transfer of Facility Operating License & Matls License & Proposed Amend, Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) ML20199K8321999-01-22022 January 1999 Forwards Request for Addl Info Re Transfer of Facility Operating License for Plant ML20199H5811999-01-20020 January 1999 Submits Exemption Withdrawal of 10CFR70.24(a) Re Criticality Accident Monitoring Requirements ML20198L7781998-12-22022 December 1998 Forwards Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted.Nrc Regional Specialists Reviewed EP & Fire Protection Programs.Ep Program Was Found to Be Well Implemented ML20198J0891998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Senator Kerry Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20198J1041998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Congressman Markey Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20137T2211998-12-17017 December 1998 Responds to to Chairman Jackson Re Concerns About Possible Sale of Pilgrim Station & Waste Disposal Issues.No Application for License Received Nor Contract of Sale Between Beco & Entergy.Record Copy ML20198J1161998-12-17017 December 1998 Responds to to Chairman Jackson in Which Recipient Expressed Concern About Possible Sale of Pilgrim Station & About Waste Disposal Issues.Nrc Has Not Received Application for Transfer of License to Date ML20198P2781998-12-17017 December 1998 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety.App B Records Being Withheld in Entirety (Ref FOIA Exemption 4) ML20198B2021998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Licensee Irpm Review.Details of Insp Plan for Next 6 Months & Historical Listing of Plant Issues Encl ML20197H8521998-12-0909 December 1998 Responds to Ltr Sent to Chairman SA Jackson on 981028 Re Concern That NRC Will Not Perform Environ Assessment in Connection with Consideration of Approval of Transfer of License for Plants to Permit Sale ML20196J1201998-12-0404 December 1998 Ack Receipt of 971217 & 30 & 980112,0309,0423 & 0630 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-293/97-02,50-293/97-11,50-293/97-13, 50-293/97-80 & 50-293/98-01.Actions Found Acceptable ML20196B5421998-11-24024 November 1998 Forwards Plant SRO & RO Initial Exam Rept 50-293/98-301OL During Wk of 981016-23 ML20196F7631998-11-24024 November 1998 Forwards Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted.Three Issues Identified Re Containment Flooding,Surveillance Testing Criteria & Protection for RBCCW System from High Energy Line Break Inside Drywell ML20196C1191998-11-20020 November 1998 Forwards Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted.During Insp Period,Chemical Decontamination of Residual Heat Removal Sys Was Well Planned & Implemented Which Reduced Radiation Doses in Heat Removal Quadrants ML20195H7361998-11-16016 November 1998 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981016 & 981019-23 at Facility.Nine Applicants Were Administered Exam & Nine Passed.Licenses Issued & Individual Test Results Encl.Without Encl ML20155C4781998-10-29029 October 1998 Forwards RAI Re Resoultion to GL 96-06 Issues at Plant,Unit 1.Response Requested by 981130 ML20154J7881998-10-0808 October 1998 Authorizes Mb Santiago to Administer Initial Written Exams to Applicants Listed (Except Applicants Redlined), on 981016.NRC Region I Operator Licensing Staff Will Administer Operating Tests During Week of 981019 1999-09-30
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,j NUCLEAR REGULATORY COMMISSION WASHtNGTON, D. C. 20555 3 p
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- gb July 15, 1986 CHAIRMAN The Honorable Gerry E. Studds United States House of Representatives Washington, D. C. 20515
Dear Congressman Studds:
In your letter of June 13, 1986 you asked a number of questions about the safety of operations at the Pilgrim Station in your district. These questions were raised in light of the accident at the Chernobyl facility in the Soviet Union.
First, I want you to know that the Pilgrim Station operations have been and are being conducted in a safe manner. The Nuclear Regulatory Commission's Region I and Headquarters staff have raised concerns that the management at Boston Edison Company may not have been as aggressive in pursuing excellence in plant maintenance and operations as they could have been.
The NRC has done a good job of identifying and following up on problems at the Pilgrim Station. The SALP report, special diagnostic team inspection, augmented inspection team and Confirmatory Action Letter 86-10, in addition to the high priority given to routine NRC inspections at Pilgrim, demonstrate that the NRC staff has e.ggressively pursued its responsibilities in protecting the health and safety of the public.
The NRC identified these concerns and brought them to the attention of government officials and the public. In that regard I would like to point out that the NRC has historically taken the initiative in keeping local government officials and the public informed as to the status of NRC activities at Pilgrim. Recent events have necessitated an expanded effort which has been accomplished through numerous meetings with state legislators, with organizations such as the Plymouth Board of Selectmen and Plymouth Chamber of Commerce, and through public meetings.
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PDR COMMS NRCC CORRESPNDENCEO PDR
i I assure you that the NRC will continue to perform its job with vigilance and will not hesitate to take those actions required to ensure the public health and safety.
Sincerely, W. % A.
Lando W. Ze , Jr.
Enclosure:
Questions and Answers i.
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QUESTION 1. What actions had the Commission taken since 1982 to assure that identified deficiencies are corrected? What specific changes in management or equipment have been made by Boston Edison as a result of Commission actions?
ANSWER.
As indicated in your letter, the NRC fined Boston Edison Company (BECo)
$550,000 in January of 1982 as a result of identified violations of NRC requirements that were attributed to management control deficiencies.
Specifically, the problems were identified in the summer of 1981 and related to specific safety systems, changes to them, and failure to maintain the systems operable. Our review at the time attributed these problems to various deficiencies associated with poor communication among several organizational elements, and a lack of management oversight. The enforcement letter highlighted a number of such issues. However, it is of significance that there were clear examples of hardware deficiencies and the lice'nsee had incorrectly informed the NRC as to changes made in the plant.
In addition to the civil penalty, the NRC also issued at that time an order that required BECo to submit to the NRC a comprehensive plan of action to address identified cor.cerns. The order required that the plan include a) an independent appraisal of site and corporate management organization and function, b) recommendation for improvements in management controls and oversight, and c) a review of previous safety related activities to evaluate compliance with NRC requirements.
BECo took several actions in response to the NRC issued order. These included a reorganization of corporate management, initiation of a Performance Improvement Program (PIP), and implementation of physical equipment upgrades.
The corporate reorganization created a new Senior Vice President position specifically for nuclear operations that reported directly to the Chief Executive Officer. Furthermore, two vice-president positions were created, one for engineering and the other for operations. This was in contrast to the prior situation where all elements of Pilgrim activities reported to a corporate officer who was responsible for all electric generation (fossil and nuclear) facilities. In addition, BECo established a nuclear oversight committee that reported directly to the Board of Directors. The PIP program addressed the issues identified in the NRC order including upgrading procedures for management control of plant configurations. The equipment upgrade program implemented by BECo was extensive and included items such as modifications to strengthen the containment, implementation of TMI Action Plan equipment upgrades, improvements in containment insulation and cooling, and other hardware improvements. NRC held management meetings with BECo approximately every six weeks until September 1984 to review progress of the PIP program.
Monitoring of its implementation was accomplished through the resident and the region-based inspectors.
In addition to those activities related to the order issued in January 1982, NRC has taken other actions with regard to Pilgrim. Since January 1982 the NRC has had eight management meetings with Pilgrim excluding those related to the
, PIP program; seven enforcement conferences have been held; three confirmatory action letters have been issued; three SALP evaluations have been performed; and over 192 inspections have been conducted. These efforts have been directed at monitoring the progress and effectiveness of BECo corrective actions, correcting identified problems and assessing performance in other areas. In essence, this level of activity is about fifty percent greater than the effort devoted by NRC Region I to similar plants in the Northeast United States.
Thus, NRC has been closely monitoring activities at Pilgrim and has taken various actions to address problems.
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, QUESTION 2. Did the Commission assign special priority to monitoring the management at Pilgrim following the precedent-setting fine in 1982? If not, why not?
ANSWER.
Yes. As indicated in the response to question 1, subsequent to issuing the Civil Penalty and Order in January 1982, NRC senior management met with BECo management approximately every six weeks until September 1984 to monitor the progress of BEco's corrective actions. The location for these meetings was rotated between the NRC Region I Office in King of Prussia, Pennsylvania, the Pilgrim plant site, and BECo Engineering Offices in Braintree, Massachusetts.
In addition, Pilgrim has received high priority in the allocation of inspection resources. For the majority of time since April 1980 the NRC has had two resident inspectors at the Pilgrim site even though it has been the NRC policy to have two resident inspectors at each reactor site only for approximately the last two years.
Pilgrim has also been given high priority in the allocation of regional based specialist inspectors. Over 16,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of inspection time have been expended at Pilgrim since the beginning of 1982. -
NRC management continues to give high priority to Pilgrim, A third resident inspector has been temporarily assigned to the facility and based on the most recent SALP results senior NRC management has reestablished periodic management meetings with BECo.
QUESTION 3. Does the Commission view it as particularly disturbing that the plant's management, three years after paying a $550,000 fine, would be found below average in three out of eight areas reviewed in a SALP?
ANSWER.
Yes, as noted in the SALP transmittal letter dated February 18, 1986 Pilgrim's
" inability to improve performance, or sustain improved performance once achieved, is of concern" to the NRC. The NRC's concern in this area is demonstrated by the high priority given to the problems at Pilgrim and by special efforts taken to evaluate the causes of these problems and determine appropriate action. An example of the special efforts taken by the NRC is the three week round-the-clock diagnostic team inspection that was conducted at Pilgrim during February and March of this year. However, it must be noted that most of 1984 at Pilgrim was devoted to the replacement of the recirculation piping in response to a Commission order; the plant was shutdown for major hardware replacement and modification. '
I QUESTION 4. Does the Commission consider a finding of below average in three out of eight areas reviewed in the 1986 SALP to constitute a serious safety concern? How much time lapsed between comp-letion of the SALP and the assignment of the special inspection team? In light of the findings of the SALP review, was con-sideration given to ordering the plant shutdown, pending the report of the inspection team? If not, why not?
ANSWER.
The 1985 SALP did not identify any specific concern that warranted NRC action to shut down the Pilgrim plant. It is important to note that there is a significant difference between cited safety deficiencies and SALP findings.
i Deficiencies that demonstratively affect safe plant operation are dealt with by
, NRC enforcement actions that can range from notices of violation to civil penalties or orders to amend or revoke a license. When enforcement action is taken a critical element in the enforcement process is NRC review of the licensee's corrective action to ensure that the corrective action will effectively correct the identified deficiency. The SALP process, on the other hand, is a diagnostic tool that is intended to identify problems in licensee performance before they result in serious safety concerns. A Category 3 rating in SALP does not mean unacceptable performance. A Category 3 rating is defined in each SALP report as follows:
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, Category 3. Both NRC and licensee attention should be increased. Licensee management attention or involvement is acceptable and considers nuclear safety, but weaknesses are evident; licensee resources appear to be strained or not effectively used so that minimally satisfactory performance with respect to operational safety is being achieved.
Thus, Category 3 ratings do not in themselves constitute immediate safety problems; however, they do identify problem areas that, if left unchecked, could develop into serious safety problems. The margin of safety that separates management problems from safety problems with plant hardware or operations is the defense in-depth philosophy that is incorporated in plant design, operation, and testing. This defense in-depth philosophy requires that numerous checks and balances be defeated before a condition exists that threatens safe operation of a plant.
Planning for the special three week diagnostic team inspection that began at Pilgrim on February 18 started immediately after the SALP Board meeting held on December 18, 1985. It was recognized at that time that special efforts were required to better understand the problems at Pilgrim. This was a unique inspection based on a relatively new approach that was used during the restart of Three Mile Island Unit 1. The inspection required significant planning and coordination of inspection resources to accomplish effectively.
Ordering plant shutdown is an option that is always available to the NRC and that the NRC has demonstrated its willingness to exercise. However, as noted above, no specific safety concern was identified during the SALP that justified ordering Pilgrim shut down. In this regard the SALP findings are based on
operations during a defined time interval, normally one year, whereas enforcement actions are taken in response to identified problems where they occur. Consequently, the SALP process is not an enforcement tool. However, SALP does allow for preventive or precautionary measures to be taken before more serious deficiencies warranting plant shutdown occur.
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QUESTION *6. Will the Commission specifically use the findings of the SALP when it reviews the operation of the plant before the anticipated resumption of plant operations next month?
ANSWER.
No. It is not appropriate to associate the current plant shutdown with the SALP resul ts . The plant is shutdown due to three specific hardware problems. Since the SALP is a historical perspective upon which we attempt to predict future '
performance, findings of the SALP process are factored into the allocation of NRC; inspection resources. Problem areas identified in SALP reports receive higher priority in inspections and consequently more inspections are conducted at problem plants. Due to recent management changes it is appropriate that more inspections occur at Pilgrim but it is not necessarily correct to assume that the 1985 SALP findings be used as the basis for either startup or continued shutdown of the plant. ,
- Note: No question 5 was identified in your letter.
QUESTION 7. Will the Commission insist on change in the organizational structure by Boston Edison that demonstrate an enhanced connitment to correcting cited safety deficiencies?
ANSWER.
BECo has on their own initiative, without the insistence of the NRC, made organizational changes intended to help resolve the problems that have been identified at Pilgrim. Specifically, a new plant manager and operations manager were hired in May of this year. In addition, in June the Senior Vice President-Nuclear was removed and the Vice President for Nuclear Operations and Vice President for Engineering and Quality Assurance now report to an Executive Vice President who also holds the title of Chief Operating Officer, who in turn reports directly to the Chief Executive Officer. We view the organizational changes as a positive indication of BEcos commitment to correct their problems and we don't foresee a need for further action at this time. ,
QUESTION 8. Will the Commission insist upon substantial improvement in the area of operator staffing levels?
ANSWER.
The licensed operator staffing problem has been affected by two factors; the workload and the low number of licensed reactor operators. The staffing of senior reactor operators has not been an issue.
As in the past, NRC will continue to monitor the operator staffing levels and on shift complements of licensed operators to ensure that the number of operators on shift and the number of hours of overtime worked by operators satisfy NRC requirements.
Six new operators (two senior operators and four reactor operators) passed the NRC administered operator licensing examinations at Pilgrim given in May,1986.
1 In addition, BEco management has new initiatives underway in recruiting and training future operators. The excessive overtime problem noted in the last SALP was the result of a low staffing level and numerous hardware modifications at the plant that required excessive operator resources to perform post modification testing. The problem of work load and resource scheduling has been acknowledged by BECo and they currently have initiatives underway to address this problem. Thus, a positive trend appears to be developing in the area of licensed operator staffing. NRC will continue to monitor this area very closely.
QUESTION 9. What other factors does the Commission view as essential to the safe startup of the facility?
ANSWER.
BECo currently requires, per Confirmatory Action Letter (CAL) 86-10, approval of the NRC Region I Administrator prior to restarting the plant. The CAL was issued in April when an Augmented Inspection Team was dispatched to the site to investigate three technical problems: leaking RHR valves, unanticipated primary containment isolations, and inability to promptly reopen the outboard main steam isolation valves following the unanticipated containment isolations.
BEco proposed resolution to these problems is currently under review by the NRC and will have to be found acceptable prior to the NRC approving restart.
BECo has decided that regardless of the CAL issues, the plant will not be restarted until they have completed an action plan that will last a minimum of six weeks. The plan is directed at certain hardware impr'ovements and at assessing and strengthening areas related to problems identified in the NRC SALP report.
During implementation of this action plan BECo has recently identified additional problems with overdue surveillance tests. A principal factor that will go into NRC evaluation of a restart of the Pilgrim reactor will be our monitoring and evaluation of the process by which the new management organization resolves problems such as the overdue surveillances and verifies the readiness of the plant for safe operation.
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