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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 ML20217J0241999-10-13013 October 1999 Documents 991005 Telcon Between NRC & Util to Address All of Areas Identified in Reg Guide 1.179 & NUREG-1700 Re Final Survey Plan Except for One Area ML20217N8371999-10-13013 October 1999 Forwards Summary of Changes Made to Maine Yankee Defueled Security Plan,Iaw 10CFR50.54(p)(2).Without Encl 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 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) 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 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10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212F4321999-09-24024 September 1999 Responds to 990921 e-mail to E Poteat,Requesting Waiver of Late Charges of Listed Amount for Annual Fee Invoice AR0431-99.Request Denied Because 10CFR15.37 Does Not Provide for Waiver Based on Info Provided in e-mail 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 ML20212M2431999-09-22022 September 1999 Expresses Concern Re NRC Consideration of Adoption of Policy Based on Requests from Licensees,To Allow as Part of Decommissioning of Nuclear Power Plants & Demolition of Onsite Structures at Reactor Plant Sites ML20212F2521999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212F1361999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212E4611999-09-20020 September 1999 Responds to Concerning Possible Involvement in Weekly Telephone Calls NRC Staff Has with Maine Yankee Staff 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) ML20212B7011999-09-14014 September 1999 Submits Comments & Raises Questions Re Generation of White Paper for Commission to Decide Merits of Rubberization 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 ML20212A5911999-09-0808 September 1999 Responds to 990816 e-mail & 990901 Telcon with Respect to Comments Re Decommissioning of Maine Yankee Site.Concerns Raised with Respect to Status of Fuel at Maine Yankee Have Been Raised in Previous Ltrs to Us NRC 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 ML20211M9371999-08-30030 August 1999 Addresses Two Issues Raised in s to Senator Collins & Governor a King That Relate to Construction of ISFSI at Maine Yankee ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant ML20212E4841999-08-27027 August 1999 Informs That at 990429 Meeting of Myap Community Advisory Panel,R Shadis,Asked If Given Lack of Resident Inspectors & Limited NRC-license Review Correspondence,If Shadis Could Take Part in Weekly NRC Conference Calls with Licensee ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211C0591999-08-19019 August 1999 Forwards Addl Justification for Proprietary Request Re 990809 Submittal Info on Maine Yankee License Termination Plan 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 ML20212A5981999-08-16016 August 1999 Expresses Appreciation for with Respect to e-mail Message Re Site Release Criteria Standards Can Never Be Verified Using Existing Database 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 ML20211D7041999-08-0909 August 1999 Forwards Rev 17 of Maine Yankee Defueled Safety Analysis Rept (Dsar), Per 10CFR50.71 & 10CFR50.4 ML20217M6501999-08-0909 August 1999 Responds to 990719 E-mail Re Cleanup Stds at MYAPC Station & Verification of Meeting Cleanup Stds.Informs That NRC Criteria for Licensing NPPs Contained in 10CFR50 & That 10CFR50.82 Addresses Requirements for License Termination ML20210Q7201999-08-0909 August 1999 Forwards non-proprietary & Proprietary Draft Documents Re Info on Myap License Termination Plan & Diskette.Proprietary Info & Diskette Withheld ML20212B2271999-08-0606 August 1999 Discusses Concerns Re Recent Incindent Involving Transport of Nuclear Matl from Maine Yankee 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 ML20210M8171999-08-0505 August 1999 Forwards Draft License Termination Plan/Amend Plan for Maine Yankee Atomic Power Co, to Enhance Dialogue Between Various Stakeholders & Provide Springboard for Clarifying Mutual Expectations.With Three Oversize Drawings ML20210L2211999-08-0202 August 1999 Forwards Two Copies of Objectives & Sequence of Events for Maine Yankee Emergency Preparedness Exercise for 990922. Without Encl 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 1999-09-09
[Table view] Category:NRC TO PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
MONTHYEARML20058C1231990-10-18018 October 1990 Responds to Which Objected to NRC Response to Inspector General Rept 90-N02 Re Emergency Preparedness. Special Task Force Established to Review Comments & Documents Presented at 900906 Meeting ML20059H3711990-09-0505 September 1990 Responds to Sent to M Miller Re Actions Taken by Util to Install Tanks on Property Adjoining Power Station. Tanks Being Installed as Part of Sewage Leach Field Sys for New Waste Treatment Facility.Nrc Has No Concerns Re Tanks ML20058M3261990-08-0909 August 1990 Responds to Re Fr Notices to Amend OL for Plant. Plant Request Consistent W/Previously Approved Requests Re BWRs & BWR Sts.Most Other BWRs Perform Logic Sys Functional Test Once Per 18 Months ML20055G7841990-07-19019 July 1990 Responds to Enclosing Article from Providence Journal Which Stated That Plant Could Operate at No More than 65% of Power While Recirculation Pump Working.License Condition Does Not Permit Continuous Single Loop Operation ML20055G3261990-07-13013 July 1990 Responds to to AR Blough Concerning NRC Findings of Reasonable Assurance Re Emergency Preparedness at Plant. Reasonable Assurance Exists Now & Existed When NRC Permitted Initiation of Power Ascension Program Above 5% Power ML20055F0541990-06-19019 June 1990 Final Response to FOIA Request.App C Records Encl & Available in PDR IA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247F0481989-07-25025 July 1989 Partial Response to FOIA Request for Records.App L Record Available in Pdr.App M Records Partially Withheld Ref (FOIA Exemption 7).App N Record Provided to Requestor But Not Made Publicly Available at This Time ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245A8151989-06-14014 June 1989 Responds to 890515 Request for Info Re 880412 RCIC Sys Event.Augmented Insp Team Concluded That Transient Minor Since Several Barriers Remained Intact to Mitigate Effects of Potential Intersystem Loss of Coolant ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 DD-89-03, Advises That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-89-03 Expired.Commission Declined Review.Decision Became Final Action on 890522.W/Certificate of Svc.Served on 8906061989-06-0606 June 1989 Advises That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision DD-89-03 Expired.Commission Declined Review.Decision Became Final Action on 890522.W/Certificate of Svc.Served on 890606 ML20246P6791989-05-0202 May 1989 Responds to Questions in Re Liability & Responsibility Requirements Under Price-Anderson Act.State of Ma Civil Defense Agency or FEMA Should Be Contacted Re Draft Implementing Procedures for Duxbury,Ma ML20244D6521989-04-17017 April 1989 Responds to to Chairman Zech Re Concerns W/Status of Emergency Preparedness at Facility.Commission Continues to Endorse Deliberate,Phased Startup Program,Over 4 to 6 Month Period,W/Augmented NRC Oversight ML20245B4051989-04-14014 April 1989 Responds to 881004 & 890119,23 & 0310 Ltrs Re Status of Investigation of Concerns About Corrosion Inhibitors & Design of Sampling Sys.Low Velocity of Liquid in Hotwell Sampling Considered Satisfactory ML20245C1501989-03-30030 March 1989 Forwards NRC Biweekly Status Insp Repts of Plant in Response to 890315 Article Re Lapse in NRC Insp Coverage.W/O Encl ML20247F6481989-03-30030 March 1989 Ack Receipt of Info Sent in Transmittal Postmarked 890218 Re NRC TLD Direct Radiation Monitoring Network ML20246M4591989-03-10010 March 1989 Responds to to Vice President Bush Re Personal Safety If Facility Permitted to Restart.Resumption of Power Dependent on Satisfactory Demonstration of Required Improvements in Emergency Preparedness ML20235R3601989-02-23023 February 1989 Discusses Review of Current Status of Licensee Power Ascension Test Program & Specific Issues Identified During 880408 Mgt Meeting ML20246N1521989-02-22022 February 1989 Responds to Re Amended Indemnity Agreement W/ Utils to Permit Storage of Spent Nuclear Fuel.Fr Notice Encl ML20206D9201988-11-0909 November 1988 Responds to Re NRC 880331 Response to Questions Raised Concerning Conditions at Plants & Recipient Proposal to Station Senior Operator in Control Room at All Nuclear Plants to Oversee Plant Operations ML20206D8871988-11-0808 November 1988 Responds to 881015 Postcard Recommending Keeping Seabrook & Pilgrim Facilities Closed & Question Re Nuclear Waste Disposal.Two Levels of Waste for Commercial Nuclear Power Plants Considered ML20195G2121988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App D Document & Releasable Portions of Documents E/1 Through E/3. App D & Releasable Portions of Documents E/4 Through E/6 Available in Pdr.Portions Withheld (Ref FOIA Exemption 5) ML20195G5361988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in PDR ML20205S0951988-11-0707 November 1988 Responds to 881015 Concerns Re Proposed Restart of Plant. Chairman Zech to P Agnes Re Expulsion from Meeting Encl ML20206B3011988-11-0303 November 1988 Forwards Util Description of Safety Enhancement Program, NRC Initial Assessment,Request for Addl Info & Util Revised Info Re Direct Torus Vent Sys,Per 881004 Discussion.W/O Encls ML20205S3841988-10-13013 October 1988 Partial Response to FOIA Request for Documents.App D,E & F Records Encl & Available in Pdr.App F Records Partially Withheld (Ref FOIA Exemption 6) ML20154Q3271988-09-27027 September 1988 Forwards Restart Readiness Assessment Rept for Facility,For Public Availability.W/O Encl ML20154Q3091988-09-27027 September 1988 Forwards Restart Readiness Assessment Rept for Facility. W/O Encl ML20154Q2811988-09-27027 September 1988 Forwards Restart Readiness Assessment Rept for Facility. W/O Encl ML20154P9021988-09-27027 September 1988 Forwards NRC Restart Assessment Panel Restart Readiness Assessment Rept for Facility.W/O Encl ML20154Q2451988-09-15015 September 1988 Forwards Integrated Assessment Team Insp Rept 50-293/88-21 on 880808-24 & SALP Rept 50-293/87-99 for 870201-880515 & Transcript from ACRS 880826 Meeting for Public Review.W/O Encls ML20154Q1571988-09-15015 September 1988 Forwards Integrated Assessment Team Insp Rept 50-293/88-21 on 880808-24 & SALP Rept 50-293/87-99.Transcript of ACRS 880826 Meeting Also Encl.W/O Encls ML20154P8861988-09-15015 September 1988 Forwards Integrated Assessment Team Insp Rept 50-293/88-21 on 880808-24,SALP Rept 50-293/87-99 for 870201-880515 & Transcript of ACRS 880826 Meeting in Plymouth,Ma & 880908 Meeting in Bethesda,Md Re Plant Restart.W/O Encls ML20154Q3521988-09-15015 September 1988 Forwards Integrated Assessment Team Insp Rept 50-293/88-21 on 880808-24,SALP Rept 50-293/87-99 for 870201-880515 & Transcripts from ACRS Subcommittee 880826 Meeting in Bethesda,Md Re Proposed Plant Restart.W/O Encl ML20154D3891988-08-22022 August 1988 Partial Response to FOIA Request for Documents.Forwards App T Documents.Apps & T Documents Available in PDR ML20151W1741988-08-16016 August 1988 Responds to 880623 Appeal of 880610 Denial of FOIA Request. Previously Withheld Record Encl.Region I Responded to Remaining Portion of Not Directly Relating to FOIA Request ML20245D6581988-08-0404 August 1988 Discusses to Congressman Hastert Re Concern That Maint & Operations Employees of Listed Nuclear Power Plants in Vicinity of Seneca,Il Working Excessive Hrs ML20206E0051988-07-27027 July 1988 Responds to Enclosing Prior Correspondence W/Nrc Re Conditions at Ref Plants & 10CFR50.54(x) & (Y).Issues Raised Will Be Given Wide Dissemination in Fr & Careful Consideration by NRC ML20151B1801988-07-0808 July 1988 Responds to Expressing Concern Re Adequacy of Highway Network Being Considered as Part of Emergency Plan. Location in Wellesley Tentatively Selected as Site for Reception Ctr.Fema Approves Adequacy of Ctrs ML20207D1121988-07-0505 July 1988 Partial Response to FOIA Request for Documents.Forwards App M Documents.App L Documents Maintained in Pdr.Apps N & O Documents Partially & Totally Withheld,Respectively (Ref FOIA Exemption 5) ML20195F8041988-06-15015 June 1988 First Partial Response to FOIA Request for Documents. Forwards Apps B & C Documents.Documents Available in Pdr.App a Documents Also Available in Pdr.Apps D Through G Documents Withheld (Ref FOIA Exemption 5).Releasable Portion Encl ML20195C6711988-06-14014 June 1988 Forwards Answers to Questions from Recipient Ref by Senator Kennedy,Per .Nrc Does Not Inspect or Monitor Animal Census & Distribution of Carcasses,Meat,Organs & Milk.Licensee Monitors Milk Samples ML20155K0211988-06-13013 June 1988 Partial Response to FOIA Request for Documents.Forwards App D Documents.App C Documents Available in Pdr.App E Documents Completely Withheld (Ref FOIA Exemption 5) ML20195C1871988-06-10010 June 1988 Forwards Info Re Provisions for Emergency Plans for transport-dependent & mobility-impaired Population,Per 880511 Request.Facilities Are Addressed within Individual Town Plans & Procedures ML20155G4301988-06-10010 June 1988 Final Response to FOIA Request for Documents.Forwards Documents Listed in App C & Releasable Portion of App D. Apps B & C Records Available in Pdr.App D Documents Partially Withheld (Ref FOIA Exemption 7) ML20151N6891988-04-19019 April 1988 Final Response to FOIA Request for Records Re Boston Edison.App a Documents Located in PDR ML20151Y4681988-04-15015 April 1988 Partial Response to FOIA Request for Documents Re Event Involving Problems W/Msiv.App a & B Documents Available in Pdr.App B Documents Also Encl ML20151H0921988-04-13013 April 1988 Expresses Disappointment w/880409 Article.Article Made Inadequate Representation of Author 880407 Conversation W/ Reporter.Incorrect Conclusions in Article Attributed to Author Ltr.Herald Should No Longer Contact Author 1990-09-05
[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 ML20212F4321999-09-24024 September 1999 Responds to 990921 e-mail to E Poteat,Requesting Waiver of Late Charges of Listed Amount for Annual Fee Invoice AR0431-99.Request Denied Because 10CFR15.37 Does Not Provide for Waiver Based on Info Provided in e-mail 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 ML20212F2521999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212F1361999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212E4611999-09-20020 September 1999 Responds to Concerning Possible Involvement in Weekly Telephone Calls NRC Staff Has with Maine Yankee Staff 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) ML20212A5911999-09-0808 September 1999 Responds to 990816 e-mail & 990901 Telcon with Respect to Comments Re Decommissioning of Maine Yankee Site.Concerns Raised with Respect to Status of Fuel at Maine Yankee Have Been Raised in Previous Ltrs to Us NRC ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant ML20211M9371999-08-30030 August 1999 Addresses Two Issues Raised in s to Senator Collins & Governor a King That Relate to Construction of ISFSI at Maine Yankee 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 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 ML20217M6501999-08-0909 August 1999 Responds to 990719 E-mail Re Cleanup Stds at MYAPC Station & Verification of Meeting Cleanup Stds.Informs That NRC Criteria for Licensing NPPs Contained in 10CFR50 & That 10CFR50.82 Addresses Requirements for License Termination ML20210G3751999-07-28028 July 1999 Ack Receipt of June 30th Ltr That Responded to EDO Backfit Appeal Determination Re Bdba in Sfps.Staff Completed All Actions Associated with Backfit Appeal & Awaiting for New Info for Consideration Prior to Taking Addl Action 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 ML20196K4751999-07-0606 July 1999 Informs That Confirmatory Orders ,830314,840614 & 960103 Have Been Rescinded.Staff Determined That Due to Permanently Shutdown & Defueled Status of Facility,Orders No Longer Necessary for Safe Operation & Maint.Se Encl 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) ML20196D9191999-06-22022 June 1999 Informs That NRC Has Completed Review of Issues Raised in of Appeal to NRC Edo.Submits List Summarizing Actions Taken Since 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 ML20207H3371999-06-11011 June 1999 Expresses Appreciation for Participation at 990413 Reactor Decommissioning Public Meeting & Responds to Concern Re Absense of Timeliness on Part of NRC Replying to Letters ML20195F6721999-06-0707 June 1999 Forwards Insp Rept 50-309/99-01 on 990214-0513.No Violations Noted.Operations & Radiological Protection Programs, Including Radioactive Liquid & Gaseous Effluent Control Programs,Were Inspected During Insp 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 ML20206U9711999-05-18018 May 1999 Responds to & Addl Info Re Appeal of NRC Determination Re Claim of Backfit Concerning Permanently Shutdown Reactor Security Plan 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 ML20207A2851999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl 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 ML20206H1391999-05-0505 May 1999 Forwards Amend 164 to License DPR-36 & Safety Evaluation. Amend Consists of Changes to License in Response to 970930 Application ML20206H2311999-05-0404 May 1999 Responds to to Chairman Jackson.Forwards Copy of Recent Staff Response to Petition Submitted on Behalf of Ucs Re Fuel Cladding at Operational Reactors ML20206G5561999-05-0303 May 1999 Forwards Amend 163 to License DPR-36 & Safety Evaluation. Amend Revises Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation 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 ML20206A5521999-04-23023 April 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Util Application Dtd 980714,for Amend to License DPR-36 to Revise App a TSs to Change Liquid & Gaseous Release Rate Limits to Reflect Revs Made to 10CFR20 ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co 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 1999-09-08
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, e31 PARK AVENUE KINO OF PnUSSIA, PENNSYLVANIA 194e6 a...*
Barbara Graves Strout 5 trout Road Poland Spring, Maine 04274 1
Dear Ms. Strout:
Thank you for your July 15, 1987 letter (a follow-up set of questions to my 1 May 28 response to your earlier inquiries).
1 It has taken us a while to respond because of the number and technical ;
specificity of your questions. We will restate each of your questions and j then give our response, which we hope will clarify these matters for you. j
- 1. Did the Nuclear Regulatory Commission notify officials at Maine Yankee l Atomic Power Plant to check whether or not they have G.E. pumps?
Specifically did the NRC notify John Arnold? Did the NRC notify Charles i Frizzle, manager of operations at Maine Yankee Atomic Power Co.? I
/
Maine Yankee was informed in Inspection and Enforcement (IE) l Information Notice No. 86-39, dated May 20, 1986, that problems existed with certain General Electric vertical induction motors based on damage to this pump at the Peach Bottom facility. The ,
damage described in this Notice was wear ring failure in the l Bingham-Willamette pump which was attached to the GE motor. _ The NRC sends out Information Notices to inform the industry of potential problems. The industry also has other mechanisms available to share j information concerning identified problems. Specific responses to 1 Information Notices are not required. Our records indicate that neither Mr. Charles Frizzle nor John Arnold were specifically addressed a copy of Information Notice 86-39; however, by sending Information Notices to all licensee's the ERC considers each licensee to have been informed.
- 2. I am requesting that if the above answer is in the affirmative, then the NRC request an answer from John Arnold and Charles Frizzle as to (yes)
Maine Yankee does have G.E. purrps or (no) it does not have G.E. pumps, and if Maine Yankee does have G.E. pumps, are they damaged?
Our inspections have determined that Maine Yankee does not have this type of pump or motor in use.
- 3. In light of all of the information included within the above listed newspaper articles are the people of Maine and New England being given the whole truth about the turbine problem at Maine Yankee?
8709140051 870901 R ADOCK OS0 g 9
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The NRC does not comment on information printed in magazines or newspapers, nor do.we review those articles for accuracy unless. the author requests it prior to publication, and that is a very rare occurrence. - The NRC, however, is concerned about problems in the ]
secondary side of .the plant that may contribute to postulated acci- 4 1
dent scenarios at' any plant. In essence, the nuclear plant produces steam. How that energy in that steam is converted into electric power-is the. licensee's' business. The NRC ensures that the impact of the secondary system on the reactor system operation is minimized._ For example, when the turbine trips from a power level above 15 perc;ent, i an automatic reactor trip occurs. The NRC would be concerned if.
repeated problems with the secondary systems cause repeated ups and l downs of the reactor systems because each trip challenges the reactor protection system. However, in this case, our reviews indicate that the licensee appears to be taking prudent action- to i resolve the vibration problems of the main' turbine' prior to placing the turbine back into continuous service. Even though this down. time is an expense for the utility in terns of replacement power, the NRC is of the opinion that resolving secondary plant problems prior to challenging automatic safety systems is sound operating philosophy,
- 4. Is the turbine problem at Maine Yankee the result of design flaws $1m11ar to those that the NRC is said to have joined General Electric Co. in keeping secret? l
.The simple answer to your question is no. Turbine vibration problems have been known at many electric generating plants, nuclear and fossil, built by manufacturers. The turbine generator at Maine Yankee exhibits vibrations when the riain turbine is running. After each outage vibration readings have been taken on the main turbine to determine the balance condition of the turbine. It is not unusual for the' licensee to add or subtract weights to the turbine in a mennes similar to balancing an automobile tire. The repair of a balance problem requires running the turbine to measure the vibra-
, tions. In order to run the turbine, the rearctor must be placed in service, main steam lines warmed, and associated secondary systems placed in operation. Once the balance weight is calculated the turbine must be stopped and the weights added. Sometimes this evolution requires shutting down the secondary side of the plant to gain access to the turbine. When this balancing effort did not resolve the latest vibration problems, the licensee searched for other clues. An analysis of vibration measurements indicated a rub in the turbine was the probable cause and the licensee initiated a program to find the components which were rthbing against each other. .
This program had three phases with the most accessible components being the first to be checked. When checks of the most accessible equipment did not uncover the source of the rubbing, the licensee continued to implement successive phases of its plan. The licensee has now entered the third phase of their investigation which requires disassembly of the low pressure turbines so as to continue the search of the rubbing components. Other information gained during the
3 testing of the turbine is being analyzed to identify the possible cause of the vibration problem. NRC inspectors are onsite following licensee action as it may affect future safe operation,of the plant, but they are not involved with the specifics of the turbine repair l effort.
- 5. These design flaws that cost utilities and their customers millions of dollars to fix. Is there any information (pro or con) on Westinghouse Electric Corp's turbine generator designs, in rel.ation to Nuclear Power Plants? J Westinghouse is one manufacturer of turbine generators. During the initial design of the plant the licensee determined what type of turbine generator he would use. The NRC is aware that turbine generators contribute to plant availability, however, the NRC does not have regulatory authority over non-nuclear safety systems and ,
therefore, does not keep records of reliability of various brands )
of turbine generators.
- 6. Can the NRC assure Maine and New England residents that starting and
. stopping this Atemic Plant and having to operate the plant at much lower
- than capacity in order to safeguard the repairs done to the turbines is safe?
Maine Yankee was operated in accordance with their Technical Spect- ' . ,
fications and operating procedures during the time the turbine was being tested. Our onsite Resident inspector witnessed a variety of tests pertaining to the operation of the plant during that timeframe.
The derating of the unit is a result of the repairs made to a low pressure turbine during the most recent cutage. During a refueling outage, a low pressure turbine is disassembled and inspected. The purpose of this inspection is to identify any deterioration of the turbines. In years past this type of inspection has identified turbine disc cracking at the keyway used to secure the blade to the disc, and blade root cracking. Corrective actions have included ,
redesign of the disc to eliminate the keyway and a different design of blade attachment to the discs. When cracks were identified in one of the low pressure turbines in the vicinity of the blade and disc attachment, an expanded program of inspections was conducted at Maine Yankee. The second low pressure turbine was disassembled and inspected for these cracks as well as the spare low pressure turbine.
Of these three turbines, one was found free of cracks. The licensee determined that the best course of action was to reuse the one good turbine and cut the cracked blading from one of the remaining low pressure turbines.
Once this blading was removed, baffles were installed within the low
. pressure turbine in order to assure that the steam flow remained balanced in the machine. The installation of the baffles resulted in the derating of the turbine. The reactor plant remains rated at full capacity. It is not uncommon to spply operational limitations on the f -
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main turbine. A number of conditions could affect the main turbine, from complex high steam flow / erosion of blade tips, to the number and capacity of feedwater pumps in operation. Some of thetse limitations may be caused by. other plant conditions. In this case the derating of the main turbine is a function of the condition of the internal components in the low pressure turbine.
- 7. Could vibrations in the turbine units cause the feedwater system to leak?
or fail? at Maine Yankeer It is unlikely that the feedwater system would be af fected by vibra-( tions in the main turbine for several reasons. The turbine rests on
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a rigidly constructed floor within the turbine building. The vibra-tions experienced in the main turbine are relatively small, causing movements of 10 to 18 mils. (One mil of vibration is 1/1000 of an inch. While this small amount of vibration could lead to premature failu)e r of the turbine, the feedwater system is designed to flex and i expand as operating temperatures increase. The feedwater piping is I supported by shock absorbers in a manner that allows pipe movement under varying conditions. Additionally, the feedwater system has been designed to accommodate such movement, a
, 8. Are the two safety systems, the ones Maine Yankee was fined $80,000 January 26 of 1986 for having inoperable for more than one year the ones that would close the plant down when the feedwater system becomes inoperable, and.the one that would shut the plant down when there is low steam pressure on the secondary side of the steam generators are they working?
The two safety systems, low steam generator (S/G) pressure trip (a trip is an automatic precautionary shutting down of a system on a
"' sensing of an abnormal condition, in this tastance, low pressure) and the feedwater trip systems are operational at Maine Yankee. Operability of these systems is required by the plant's Technical Specifications during certain operating conditions. These two systems provide for a special set of potential conditions at Maine Yankee. The NRC requires each licensee to analyze its plant under various accident conditions. One of these accident conditions is called a Steam Line Break Accident. If a pipe carrying steam were to break, the resul-tant cooling down of the reactor system and the release of the steam energy into containment could lead to premature failure of the containment system and ultimately the release of radioactive fission products to the atmosphere. In order to protect against such an accident, the licensee must show that if this accident were to occur,
,/ the plant would automatically function to eliminate the possibility !
/ of this overpressurization of the containment building. The low $/G i pressure trip function is designed to sense a low pressure condition that would exist during a $ team Line Break Accident and shutdown the i plant. Additionally, the feedwater trip system receives an input i g from the low S/G pressure and isolates the feedwater to that $/G. '
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V This is important because adding additional water to a faulted $/G with a break inside of containment would only cause the pressure inside of containment to rise in excess of the design 5ressure of the containment building.
The Civil Penalty that was imposed upon Maine Yankee was for not ,
having the required number of low pressure detectors available during an operating condition when they were required to have them and hailing one channel of the feedwater trip system inoperable for a different reason. Details of these events are described in NRC Inspection Reports 85-19 and 85-27 which are available in the Wiscasset Library, where the NRC has put the public document room for '
Maine Yankee.
One question that you asked in the beginning of your letter was how could 37 inspections conducted in 1985 fail to identify an inoperable system for over a year. The NRC Resident Inspection Program assigns one or two residents at each site. Although these inspectors make daily tours and system walkdowns through-out the plant, they do not operate equipment. That is the sole responsibility ;
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of the utility. If operation of valves or equipment by just anyone was '
permitted, then operability of essential equipment could not be ensured. Of the 37 inspections conducted during that year, two inspections focused on the events surrounding the discovery of two inoperable systems but they were con-ducted after the licensee discovered the condition. The discovery of the shut root valves was.only made after those valves were repositioned. The discovery of the problem with the remaining channel of low pressure protection was made during the conduct of an NRC required surveillance to check the setpoints of the trip system. In each case, it is not feasible that an NRC inspector would have identified the condition. The NRC requires each licensee to report deficient conditions to the NRC in accordance with strict guidelines, j The low )ressure valves that were found closed were only identified after troubles 1ooting deficiencies.in pressure indication. In fact, even though f i
the valves were discovered closed, there was enough leakage past the the '
valves to provide normal indication of pressure to the control room operators.
During the Enforcement Conference between the NRC and the licensee it was determined that sufficient redundancy existed in the Reactor Protective System to provide for a plant trip during the steam line break accident scenario without the low pressure detectors in service. The NRC acknowledged the redundancy but did not credit the plant for the redundant systems since they were required to have the luw pressure detectors operable. The feedwater trip system war also a subject of that Enforcement Conference. The feedwater trip system receives some of its information from the low pressure detectors. Since the detectors were considered inoperable, the feedwater trip system was also inoperable. The licensee showed that the affect of not isolating feedwater .
during a steam line bred accident was no worse than what the NRC had approved l for other plants. The LM did not accept this argument since Maine Yankee was l not licensed to this different criteria. Therefore, although the licensee showed that in each case there were redundant systems available and that the the overall affect of a steam line break accident was within acceptable limits, !
the NRC still imposed a $80,000 Civil Penalty since the plant did not meet the '
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requirement in its license. ' All oilhese ana' lyses did not take credit for operators, who could have used other instrumentation arid equipment controls to mitigate the effects of a steam line break. .
I believe that covers all the points you raised. Please contact me again if we can be of further assistance.
Sincerely, M
, Karl Abraham Sr. Public Affairs Officer NRC Region I Office of Governmental and Public Affairs CCI The Honorable George J. Mitchell, United States Senate The Honorable William S. Cohen, United States Senate The Honorable Olympia J. Snowe, United States House of Representatives
. The Honorable Joseph Brennan, United States House of Representatives The Honorable William R. Sharp, United States House of Representatives
, Chairman, Subcommittee on Energy and Power The Honorable John R. McKernan, Jr., Governor of Maine The Honorable James Tierney, Attorney General, State of Maine C. E. Monty, President C. D. Frizzle, Assistant Vice President / Manager of Operations J. H. Carrity, Plant Manager P. L. Anderson, Project Manager G. D. Whittier, Licensing Section Head l J. A. Ritsher, Attorney (Ropes and Gray) '
Phillip Ahrens, Esquire Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Maine I
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- FOR ' SIGNATllREI OF:-- ** GREEN *F. SFCY NO: 87-0934 ;
TRUSSELL; iDESC: ROUTING: a CNCI. LETTER FM BARBARA' GRAVES STROUT'RE MURLEY. NRR.
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- ASSIGNED TO: RI CONTACT: RUSSELL iSPECI AL ' INSTRUCTIONS OR RFMARKS: .q
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.t- 1 OFFICE OF THE SECRETARY i CORRESPONDENCE CONTROL TICKET l 1 PAPER NUMBER: ' CRC-87-0934 LOGGING DATE:Jul'31 87 .
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' ACTION OFFICE: EDO' L'.. AUTHOR: P.R. Sharp--Const Ref j '
. AFFILIATION: .-U.S. HOUSE OF REPRESENTATIVES 1 LETTER DATE:~ Jul 27 87 FILE CODE:
SUBJECT:
. Problems with. General Electric pumps--ref Pilgrim .l and Maine. Yankee. plants j ACTION: Direct Reply DISTRIBUTION:. OCA to Ack )!
SPECIAL HANDLING: None NOTES: Barbara Graves Strout 4 1
DATE DUE:- Aug 14 87 SIGNATURE: .. 'DATE SIGNED:
' AFFILIATION:
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