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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1851999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request ML20212F8341999-09-22022 September 1999 Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 ML20210U2621999-08-12012 August 1999 Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds ML20216D9421999-07-28028 July 1999 Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal ML20210A7001999-07-16016 July 1999 Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20209D5511999-07-0606 July 1999 Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept ML20196G2981999-06-18018 June 1999 Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant ML20196L1451999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) ML20207D9191999-05-27027 May 1999 Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl ML20207A6751999-05-17017 May 1999 Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls ML20206N0721999-05-11011 May 1999 Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20206C8551999-04-27027 April 1999 Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205P1991999-04-0909 April 1999 Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARJPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JPN-99-011, Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing1999-04-0505 April 1999 Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing ML20205G4111999-03-31031 March 1999 Forwards Rev 7 to JAFNPP EP App J & Rev 6,pages 7 & 8 to EAP-5.3 05000333/LER-1999-001, Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments1999-03-31031 March 1999 Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments JPN-99-008, Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl1999-03-31031 March 1999 Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl JPN-99-010, Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP1999-03-31031 March 1999 Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP JAFP-99-0114, Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl1999-03-29029 March 1999 Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl JAFP-99-0112, Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested1999-03-29029 March 1999 Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested JAFP-99-0097, Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years1999-03-17017 March 1999 Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years ML20204B6241999-03-17017 March 1999 Forwards Plant Referenced Simulation Facility Four Year Performance Testing Rept, Per 10CFR55.45(b)ii 05000333/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept1999-03-16016 March 1999 Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept ML20204C7371999-03-15015 March 1999 Forwards Revised EP Coversheets for Sections to Vol 1 & Rev 26,Vol 3 to EPIP SAP-10, Meteorological Monitoring Sys Surveillance JAFP-99-0085, Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable1999-03-0808 March 1999 Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable ML20207J3201999-03-0505 March 1999 Forwards Form NRC-369,requesting That Restriction for Corrective Lenses Be Placed on Current License SOP-10089-3, for Ks Allen.Encl Withheld Per 10CFR2.790(a)(6).Without Encl JAFP-99-0073, Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments1999-02-26026 February 1999 Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments JAFP-99-0071, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-02-25025 February 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0068, Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting..1999-02-22022 February 1999 Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting.. JAFP-99-0019, Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS1999-01-25025 January 1999 Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS JAFP-99-0012, Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys1999-01-18018 January 1999 Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys 1999-09-08
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20247F8061989-07-0505 July 1989 FOIA Request for Documentation Re Incidents of Drug &/Or Alcohol Abuse During Past Five Yrs Amoung Employees or Contractors ML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20080K4321983-09-12012 September 1983 Requests Immediate Plant Shutdown Due to Concerns Re Adequacy of Piping Supports.Supports May Not Be Able to Withstand Normal Operating Loads.Util Has Known of Problem for 3-4 Yrs ML20080S8571983-08-11011 August 1983 FOIA Request for Target Technology,Ltd Documents Re Pipe Supports ML19312B6191979-03-23023 March 1979 Requests Order Stating Date,Time & Place of ASLB Facility Hearing ML19289E9081969-05-0707 May 1969 Suggests Subsurface Explorations in Bedrock & Soils to Reveal True Stratigraphic & Structural Conditions Prior to Const.(Author'S Name & Affiliation Deleted) 1989-07-05
[Table view] |
Text
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. 00CMETED JS MC UNION OF CONCERNED 83 e 12 m 2a SCIENTISTS Im Canu*uuvenue, N.W. . S. Hot . W k 6Cm36. (m) m.5600 September 12, 1983 Nunzio Palladino, Chairman James Asselstine, Commissioner Frederick Bernthal, Commissioner Victor Gilinsky, Commissioner Thomas Roberts, Commissioner U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
UCS has received information which indicates the presence of a grave safety hazard at the FitzPatrick nuclear power plant operated by the New York Power Authority. We believe that similar hazards may exist at other plants designed and built by the same architect-engineer involved in the FitzPatrick plant.
Included in the information we have obtained concerning the FitzPatrick plant is a letter from Mr. John Dainora, President of Target Technology, Ltd.
to Mr. Leon Guaquil, New York Power Authority, dated June 30, 1983 A copy is enclosed.
J l
In 1979, when FitzPatrick was one of five nuclear plants ordered to shut l
l down because of Stone & Webster's miscalculation vf the seismic stresses on piping, Target Technology was hired by the New York Power Authority to re-analyze the pipe supports. According to the enclosed letter, Target l
l I
1 8309290153 030923 PDR ADOCK 05000333 0 PDR j 51ain Office: 26 Church Street . Cambridge. 31assachusetts 02238 . (617) 547 5552
Technology informed the Power Authority at least 3 years ago (9/3/80) that the overall task of bringing the pipe supports into compliance with the Code requirements and the commitments made by the Power Auth rity in its Final Safety Analysis Report was incomplete. The Authority made no response. On December 20, 1982, Mr. Dainora again wrote to the Power Authority stating that there were 348 pipe supports for which Target Technology was the Engineer-of-Rscord and for which the stress calculations were incomplete. The June 30, 1983 letter is Target Technology's latest attempt to persuade the Power Authority to take action. Mr. Dainora states: " As a specialist in the piping area, I am convinced that unless you do something in the very near future, the plant will have a major Loss-of-Coolant Accident within the next three years."
(p.4, emphasis in original)
As we interpret the letter, it raises the following concerns:
- 1. A large number of pipe supports in the FitzPatrick plant may not be able to withstand normal operating loads.
Mr. Dainaro stated that some of the supports " clearly exhibit physical signs of structural damage from normal operating loads and have safety implications for the plant." (p.2, emphasis in original) Thus, this problem is obviously not simply a hypothetical one. Furthermore, in many instances the Power Authority is apparently relying on the original design analysis of normal operating loads. This is inappropriate because the original calculations are unavailable, the "as-built" plant does not match the pipe configuration initially analysed, and supports have been added or deleted since. (See Item #5, p.3) t
. ,. --- . ~ . - . . _ . . _ .
- 2. In 1979, when Target Technology discovered pipe supports which were not adequate for normal operating loads, it was directed by the Power Authority and Stone & Webster not to consider normal operating loads and to change the acceptance criteria.
Mr. Dainora stated: "We were told by the Authority and Stone & Webster in 1979 not to do that [ consider the normal operating loads] because we found supports which were failing the allowable stress limits for the normal operating condition." (p.2) In May 1979, Target Technology proposed pipe support design criteria to be used in evaluating the FitzPatrick plant. Mr.
D2inora stated : "Because some of the support designs did not pass the normal operating loads, we were instructed by the Authority and Stone & Webster to change the criteria." (p.3)
- 3. A large number of pipe supports in the FitzPatrick plant may not meet the commitments regarding earthquake stresses made by the Authority in its Final Safety Analysis Report for obtaining the operating license.
Mr. Dainora noted that in the FSAR, the Authority had committed to d2 sign pipe supports in accordance with the requirements of ANSI B31.1.0-1967.
l However, the original Stone & Webster design was based on the American l Institute of Steel Construction ( AISC) Code . (See p.4) The significance of this is that supports found acceptable using the AISC Code could be stressed above the allowable limits for earthquake loading that would apply if the ANSI B31.1 Code were used. Mr. Dainaro noted that in 1979 the Power Authority had reported to the NRC that "[alll calculated stresses are checked against allowables specified in ANSI B31.1." However , Mr. Dainaro stated : " This i
statement is consistent with the original SAR commitments.. . . but inconsistent with what was actually done." (p.4)3./
- 4. The Power Authority has known of the problems identified by Target Technology for at least 3 and very probably 4 years.
10 CFR 21.21 requires any licensee to " notify the Commission when he obtains information reasonably indicating a failure to comply or a defect affecting: (i) The construction or operation of a facility...." Initial notification of the defect or noncompliance is required within two days of receipt of the information.
The Dainora letter indicates that the New York Power Authority has been on written notice of this information since at least September of 1980.
Moreover, the consultant, a specialist in the piping area, clearly considers the matter to be of great safety significance. He states that he expects a major LOCA within three years unless the matter is immediately addressed.
(p.4) One can scarcely imagine language more serious than that used by the consultant: "Outside of appealing to your sense of professionalism, concern for public safety, and the potential for a huge economic loss, there is not much more than we can do." (p.3) 1_/ UCS has also identified inconsistencies between the Authority's statements to the NRC and information provided by Target Technology. For i
example, in seeking to restart the FitzPatrick plant in 1979, the Authority reported to NRC that "[a]ny damage to or deterioration of pipe supports was noted, evaluated, and repaired or modified as necessary." (Letter from Paul Early to NRC, August 2, 1979, p.2) This is inconsistent with Mr. Dainaro's statements that supports which clearly exhibited structural damage from normal operating loads remained in the plant after restart in September 1979
Nonetheless, no recort under Part 21 has been made to NRC by the Power Authority.
UCS has located only one letter from the Power Authority to the NRC on this subject which is dated July 7, 1983 A copy is enclosed. That letter is so vague that it could be fairly characterized as deliberately deceitful. Mr.
J. Phillip Bayne states that the Power Authority has been informed of a potential noncompliance but gives no indication of when they were so informed.
Indeed, Mr. Bayne gives the false impression that this is new informatien by stating that "[t]he ' Authority is taking immediate action to evaluata the potential nonconformance." It was also stated that "[t]he Power Authority will complete the evaluation of the potential nonconformance prior to startup from the current refueling outage, and inform the NRC of the results."
Although UCS is aware that the FitzPatrick plant has recently resumed operation, we have been unable to determine whether and, if so, how the Power Authority resolved the problems identified by Target Technology. It seems highly questionable that the problems could have been properly resolved in the short time available.
- 5. The potential exists that supports in other plants designed and constructed by Stone & Webster are overstressed under normal operating loads.
The problems which led to the 1979 shutdown of Beaver Valley Unit 1, Surry Units 1 and 2 Maine Yankee and FitzPatrick were first discovered at Beaver Valley. Subsequent investigation determined that Stone & Webster had used an incorrect computer code to calculate pipe stresses at all five plants.
Znspection of the shutdown plants revealed significant differences between the original designs and the "as built" configurations of the piping systems.
- e-Since pipe supports which may be overstressed for normal operating loads have been found at the FitzPatrick plant, and since Stone & Webster was the architect engineer and constructor of all five plants, the Beaver Valley Unit 1, Surry Units 1 and 2, and Maine Yankee plants may have similar conditions of safety significance.
Because of the obvious safety implications of this matter, UCS is bringing it to the Commissioners' attention for immediate action. The letter was released to us by the NRC on September 8,1983 pursuant to a Freedom of Information Act request. On that day, FitzPatrick was in the process of ascending to full power after a refueling outage. We do not know how long the letter has been in the possession of the Staff. UCS telephoned Mr. Dainora on the afternoon of September 8 and confirmed the accuracy of the letter. In cddition, Mr. Dainora told us that he has never been contacted by the NRC. It is therefore quite apparent that action at the Commission level is necessary.
Because 1) Mr. Dainora has informed us that many of the pipe supports are inside containment or otherwise inaccessible while the plant is operating,
- 2) physical damage has been observed and the problem has persisted for many years and 3) the Power Authority h.as failed to inform NRC of Mr. Dainora's concerns for more than three years, UCS urges you to immediately order the FitzPatrick plant to shut down to enable full NRC inspection of the questionable supports. The plant should not be allowed to resume operation until the NRC confirms that the FSAR committments and the requirements of I&E Bulletins 79-7 and 79-14 have been met.
The Coor.lssion should also expeditiously determine who on the NRC Staff has been in possession of Mr. Dainora's letter of June 30, 1983 anc for how long, and why Mr. Dainora was never contacted by the NRC. While the New York
e Power Authority claims to have hired a third party to ' review and evaluate the potential nonconformance", we are informed by M,r. Dainora that he has not been contacted to determine whether his concerns have been resolved.
Finally, the information presented constitutes in UCS's view prima facie evidence of violation by the Power Authority of the reporting requirements of 10 CFR 21 and also raises a question as to whether the Authority may have made a material false statement in certifying to NRC that all calculated stresses were checked against the allowables specified in ANSI Code B31.1. The Commission should begin appropriate enforcement action.
UCS requests that we be kept informed of the action which you take in this matter.
Very truly yours, Ellyn R. Weiss General Counsel Robert D. Pollard Nuclear Safety Engineer Union of Concerned Scientists Enclosures cc: Mr. J. Phillip Bayne Executive Vice President Nuclear Generation New York Power Authority 123 Main Street White Plains, New York 10601 Mr. John Dainora, President Target Technolcgy Ltd.
222 West Lancaster Avenue Paoli, Pennsylvania 19301
., TARGET TECHNOLOGY LTD. Y 222 WEST LANC ASTER AVENUE
- P AOtt. PENNSYLV ANI A 19301 (2153 296 7340 JOHN D A.1Noa.A
June 30, 1983 Mr. Leon Guaquil Director, Project Engineering-BWR tiew York Power Authority 123 Main Street ,
White Plains, New York 10601
Subject:
James A. FitzPatrick fluclear Power Plant '
Design tion-Compliance with Final Safety Analysis Report (FSAR)
Dear Leon:
My initial letter to the Authority (Reference 1) dated 9/3/80 was motivated by the fact that the activity for compliance with the requirements of I&E Bulletins 79-02, 79-07 and 79-14 to an Interim Criteria (normal / upset loads + seismic) was coming to a close and therefore it appeared timely to close-out the overall activity by bringing the pipe supports to compliance with F;AR comitments and Code require-ments before disbanding the assembled project team. I also wanted to make sure that the Authority clearly understood, because of safety implications, that the task was incomplete and additional effort would..be required to complete it.
After a couple of years of waiting for a response to my initial letter, I sent a follow-up letter dated 12/20/82 (Reference 2) addressed to you. My concerns at the time of the.second letter were based on the fact that we were the Engineers-of-Record for 348 s'upports in the plant which had calculational packages that we
' consider to be incomplete from the standpoint of industry practice, as well as Code
- and flRC requirements. We wanted to be absolutely sure that in the event of a l post-accident inquiry that at least the work that we had performed was complete and representedourbestef4 orts.
At your request, we telecopied to you on 1/3/83 the following list of 20 supports which had an earthquake loading component less.than 33 percent-of the total load, and therefore have the potential of not meetino' the Code allowable l limits for the normal loading condition.
MSK ll4U H10-522 MSX 137G H46-1A MSK ll6C Hil-2 MSK 127A H29-141 MSX ll4U H10-214 MSX 127A H29-23 MSK ll6C Hil-1 MSK 127A H29-349 MSK ll7F H14-55 '
MSX 1278 H29-21 MSK 114F BZ-14C MSX 1278 H29-348 MSX ll4F H10-40A MSX 127C H29-27' MSX 117A H14-4 9 MSX 127C H29-351 MSK ll4J H10-215 MSK 1270 H29-25 MSK 101A H12-52 MSK 1270 H29-350
I !
., June 30, 1983 l
Nr. l.co'n Guaquil Page 2 3ew York Power Authority .
I t was The Engineer-of-Record for the above supports is Stone & Webster.
important for us to establish the cuality of the sample Includedreview which in the above you under and the reasonableness of the conclusions you reached.
~
Our list were
- from normal coeratino loads _ and have safety implications for the plant.if
, pre-estaclished position was thatbill of health then additional technical dialog not produce any significant results.
Our meeting on 6/27/83 at Stone & Webster's offices to discuss I ammy concerns sure included senior management from the Authority and Stone & Webster.
However, I would like to offer my co=ents and observation discussion which took place:
Trem fl. Stone & Webster indicated that for the supports and are satisfied.
Authority's The validity of this statement is the Cement: responsibility to assess and to act on the basis of their conclusions.
Stone & Websler reviewed the sample list of 20 supports provided Item #2.
by TARGET and found all of them to be acceptable.
Given the fact that some of the supports show evidence Coment: of physical damage from normal operating loads, the On the other statement appears to us .to be incredible.
hand, we are aware that TARGET is only a small consulting company and we do not claim to have the depth of technical expertise to challenge an industry leader such as Stone &
Webster.
TARGET should have considered the normal operating loads at the tim Item #3.
that they did the calculations.
We were told by the Authority and Stone & Webster in 1979 Coment: specifically not to do that because we found supports which were failing the allowable stress limits for the normal operating condition. Because at the time of this activity our contract was on a time and material basis, there was no reason for us to do less than required.
Item ca.
No safety implications are implied because even for the case of zero earthquake loading the most that the code allowable limits would be exceeded would be 33 percent.
9
'. . TARGET TECHN6 0GY LTD.
Mr. Leon Guaquil ' June 30, 1983 Nev. York power Authority Page 3 Coment: An appealing generalization on the surface--however, it does not account for the fact that some of the supports appear to be already overloaded.
Item #5. The supports were initially designed by Bergen-Patterson for normal operating loads and since the show cause order was directed to earthquake effects, the supports must be OK for normal loads.
Coment: An illogical conclusion that is not supported by fact when the following is considered: -
(a) Because the maiority of the Bergen-Patterson calculations are not available--what was actually done during plant construction is an unknown.
(b) The support loads changed dramatically for many supports because the as-built condition of the plant did not match the piping ccnfigurations which were initially analyzed. -
(c) Supports were added or deleted to' systems.
Item #6. TARGET has not evaluated.the 348 support designs for which they are the Engineer-of-Record for normal operating loads.
Comment: Outside of appealing to your sense of professionalism, concern for public safety, and the potential for a huge economic loss, there is not much more than we can do. However, if the Authority elects not to review the 348 support designs for normal operating loads, they also must assume 100 percent of the responsibility and the legal consequences.
In our brief discussion on this subject after the conclusion of the formal portion of the meeting you requested background material and a cost estimate for doing the work.
The estimated cost for doing Our proposal is presented as Attachment "A".
the work is $74,500. If you decide to request us to perfon:: the assignment , we will accomplish the task with our usual professional pride and integrity.
The background material which may be useful to your decision making process is enclosed as follows:
Reference 3: Pipe Support Design Criteria - Dated 5/23/79.
Comment: The initial criteria proposed by TARGET. Because scme of the support designs did not pass the norral operating loads, we were instructed by the Authority and Stone & 'rlebster to change the criteria.
9
s
.' TARGET TECHNdLOGY LTD.
Nr. i. eon Guacuil . June 30,1983 tiew York Power Authority page 4 Reference 4: fiotes of Telephone Conversation - 5/25/79.
Comment: TARGET was trying to establish what design criteria to be used. Also note G. Arena's (S&W) comment that except for components welded directly to the pipe, all other components were considered in the original design to be within the jurisdictional boundaries of the AISC Code.
Reference 5: TARGET's Checking and Modification Design Criteria for Pipe Supports - dated 5/26/79. -
Co=ent : This criteria was reviewed and approved by the Authority.
Note that any consideration of normal . operating loads was deleted per the direction of Reference 4. '
Reference 6: SAR Excerpt. , page Q.4.1-1 Coment: Note co.mitment to design supports to ANSI B31.1.0-1967.
This comitment is inconsistent with G. Arena's coment in Reference 4. The importance of G. Arena 's co=ent was that he was the only available S&W spokesman who had actually worked on the original plant design.
Reference 7: PASNY report to the' NRItfansmitted via letter JPN-79-48 (Page 4-5)
Comen t: Note the statement that "All calculated stresses are checked against allowables specified in ANSI B31.1." This statement is consistent with the original SAR comitments (see Reference
- 6) but inconsistent with what was actually done.
In closing, let me say that I understand your problem as a technical manager in sif ting through the conflicting statements. On the one hand, you have a small consulting company telling you that the situation as it currently exists requires corrective action, while on the other hand a cajor.A/E firm who built the plant initially is telling you not to worry about it--everything is alright.
In my situation the problem is slightly different. As a specialist in the
~
piping area , I am . convinced that unless you do something in the very near future, the plant will have a major Loss-of-Coolant Accident within the next three years.
Waiting for an accident to happen to be proven technically correct seems like an absurd way of accumulating professional credits.
9
. TARGET TECHNO 0GY LTD.
s Ar. Leon Guaquil '
June 30,1983 flew York Power Authority . Page 5 Leon, I have had my final say on this subject. The ball is back in your court. You co wha t yvt, think is best for you, four employer, the nuclear industry and the general public.
Yours very truly, TARGET TECHNOLOGY LTD.
ohn Dainora President JD:eh Enclosures cc: Mr. R. Burns (fiYPA) -
Mr. J. Leonard (NYPA)
I i
l 9
.'* , 11 23 Man Street yht2 %ns. NIw WA 10601 914 681.6240
.O NewYorkFower
<d Authority j P E '" " =:?::"A.
'83 JUL 18 P2:15 IH 65 Q PUBLiC uw - - ~ 2'i Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
~.
Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Potential = rig = suaso&_-Design Nonconformance
Dear Sir:
The Power Authority has been informed 'oy one of our technical consultants of a potential nonconformance in the reanalysis of 348 pipe supports installed in the Fit: Patrick plant. The potential nonconformance involves only the design of the supports for normal loads. The design of tne supports for seismic loads was completed in accordance with the applicable codes, standards and metnodology approved by the NRC.
Therefore, the seismic design of tne pipe supports is not in question. The consultant has also identified approximately 20 additional supports which may be affected.
The Authority is taking immediate action to evaluate the
-. . potential nonconformance. A visual inspection of the twenty l "'
- potentially af f ected pipe supports is in progress. The s
Authority will employ another consultant, not previously involved in pipe support analysis for the Fit: Patrick plant, to review and evaluate the potential nonconformance. The Authority's preliminary determination, which is based on the l information now available and therefore wnicn is subject to l change, is that evaluation of this potential nonconformance is unlikely to show a condition wnicn is reportable under 10 CFR 21.
l l
l
\
- 9?O711'0309-0307D7 PDR ADO M 50DD333 I
S e PDM ij Q
. . . 3 The Fit: Patrick plant is currently i~n the cold condition for a refueling outage. Most of the potentially affected pipe supports are not subject to the loads f or which their design has been questioned.
Therefore, the health and safety of tne public are not affected.
The Power Authority will complete the evaluation of the potential
nonconformance prior to atartup from the current refueling outage, and inform the NRC of the results.
If you have any further questions, please contact Mr. J. A. Gray, Jr.,
of my staff.
Very truly yours, ,
'N I
Jj .
-~ Executive Vice President ,
Nuclear Generation cc: Mr. Harry B. Kister United States Nuclear Regulatory Conmission
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Region I 531 Park Avenue King of Prussia, Pa., 19406 Mr . J . Linville Resident Inspector U.S. Nuclear Regulatory Commission l
P.O. Box 135 Lycocing, NY 1309 3 l
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