|
---|
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:UTILITY TO NRC
MONTHYEARJPN-90-063, Responds to NRC Re Deviations Noted in Insp Rept 50-333/90-19.Interim Corrective Action:Temporary Procedure Change Implemented to Administratively Prohibit Concurrent Closure of Upstream Feeder Breakers Until Issue Resolved1990-09-18018 September 1990 Responds to NRC Re Deviations Noted in Insp Rept 50-333/90-19.Interim Corrective Action:Temporary Procedure Change Implemented to Administratively Prohibit Concurrent Closure of Upstream Feeder Breakers Until Issue Resolved JPN-90-061, Forwards Analyses Re Installation of Hardened Wetwell Vent, Including Benefits of Elevated Vs Ground Level Gas Release. Analyses Provide Further Evidence That Addition of Elevated Release to Existing Hardened Vent Not Cost Beneficial1990-09-0707 September 1990 Forwards Analyses Re Installation of Hardened Wetwell Vent, Including Benefits of Elevated Vs Ground Level Gas Release. Analyses Provide Further Evidence That Addition of Elevated Release to Existing Hardened Vent Not Cost Beneficial JPN-90-060, Forwards Info to Satisfy 900716 Commitment Re Switchgear Deficiency,Per SSFI Insp Rept 50-333/89-80.Waiver Requested Re Design Requirements for Three Phase Bolted Fault Criteria for Switchgear Configuration for Diesel Generator Testing1990-09-0404 September 1990 Forwards Info to Satisfy 900716 Commitment Re Switchgear Deficiency,Per SSFI Insp Rept 50-333/89-80.Waiver Requested Re Design Requirements for Three Phase Bolted Fault Criteria for Switchgear Configuration for Diesel Generator Testing JPN-90-057, Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station1990-08-14014 August 1990 Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station JAFP-90-0581, Forwards Proposed Rev 6 to IAP-2, Classification of Emergency Conditions, Per Insp Rept 50-333/90-15,Unresolved Item 89-11-03.Rev Incorporates Changes Assuring That Applicable Initiating Conditions,Per NUREG-0654,addressed1990-07-30030 July 1990 Forwards Proposed Rev 6 to IAP-2, Classification of Emergency Conditions, Per Insp Rept 50-333/90-15,Unresolved Item 89-11-03.Rev Incorporates Changes Assuring That Applicable Initiating Conditions,Per NUREG-0654,addressed JPN-90-055, Forwards Comments on Installation of Hardened Wetwell Vent at Plant,Per 891027 Response to Generic Ltr 89-16.Concludes That Hardened Vent Not Cost Beneficial & Consideration of Mods Be Deferred Until Individual Plant Evaluation Complete1990-07-25025 July 1990 Forwards Comments on Installation of Hardened Wetwell Vent at Plant,Per 891027 Response to Generic Ltr 89-16.Concludes That Hardened Vent Not Cost Beneficial & Consideration of Mods Be Deferred Until Individual Plant Evaluation Complete 05000333/LER-1990-012, Advises That Suppl Rept to LER 90-012 Re Svc Water Check Valves Will Be Submitted by 9008201990-07-18018 July 1990 Advises That Suppl Rept to LER 90-012 Re Svc Water Check Valves Will Be Submitted by 900820 05000333/LER-1989-012, Advises That Suppl to LER 89-012-00 Re Postulated Fault 4 Kv Bus Fault Will Be Submitted by 9009041990-07-16016 July 1990 Advises That Suppl to LER 89-012-00 Re Postulated Fault 4 Kv Bus Fault Will Be Submitted by 900904 ML20044A9311990-07-0606 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Rept 50-333/90-17.Corrective Action:Suspended Surveillances Reinstated on 900507 ML20043J0101990-06-21021 June 1990 Forwards Application for Amend to License DPR-59,making Temporary Change Re LPCI Pump Flow Permanent,Per 900228 Ltr. Change Reduced Surveillance Test Flow Acceptance Value for RHR Pump JAFP-90-0468, Informs That Licensed Operator Requalification Training Program at Plant Completed Transition to Program Based on Sys Approach to Training as Ref to in 10CFR55.4 & 591990-06-14014 June 1990 Informs That Licensed Operator Requalification Training Program at Plant Completed Transition to Program Based on Sys Approach to Training as Ref to in 10CFR55.4 & 59 ML20043G2491990-06-12012 June 1990 Forwards Application for Amend to License DPR-59,revising Tech Specs to Reflect Containment Isolation Valves in RHR & Core Spray keep-full Sys ML20043F5931990-06-11011 June 1990 Forwards GE Nonproprietary Rept, GE11 Lead Test Assembly Fo Ja Fitzpatrick Nuclear Power Plant Reload 9 Cycle 10 & Proprietary Rept GE11 Lead Test Assembly Fuel Bundle.... Proprietary Rept Withheld (Ref 10CFR2.790) ML20043G6131990-06-11011 June 1990 Responds to Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $75,000 Re Radiation Exposure. Corrective Actions:Worker Decontaminated & Examined by Physician.Civil Penalty Fee Transferred Electronically ML20043H0851990-06-11011 June 1990 Forwards Reload 9/Cycle 10 Core Operating Limits Rept. ML20043G7561990-06-11011 June 1990 Forwards Application for Amend to License DPR-59 Re Performance Discharge Testing of 125-volt Dc Batteries & LPCI Motor Operated Valve Independent Power Supplies ML20043H0451990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-333/90-02.Corrective Actions:Refuel Floor Work Stopped, Chief Radiation Protection Technician Disciplined & Importance of Following Procedural Guidelines Reinforced ML20043E8911990-06-0707 June 1990 Forwards IGSCC Insp 1990 Refueling Outage Summary Rept Addendum ML20043C3381990-05-31031 May 1990 Forwards Application for Amend to License DPR-59,revising Tech Spec 5.5.B to Increase Number of Spent Fuel Assemblies That Can Be Stored in Spent Fuel Pool ML20043C5091990-05-30030 May 1990 Forwards Application for Amend to License DPR-59,updating Tech Spec Tables 3.2-8 & 4.2-8 to Reflect Installation of post-accident Monitoring Instrumentation,Per Reg Guide 1.97 & Deleting Tables 3.2-6,4.2-6 & 4.7-1 ML20043C7411990-05-25025 May 1990 Forwards Structural Evaluation of Indications in Reactor Top Head at Ja Fitzpatrick Power Station, Based on Evaluation Analyses for Flaw Indications Identified During Routine Inservice Insps ML20043A7681990-05-16016 May 1990 Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Channel Boxes Not Reused After First Lifetime.Methodology Developed by Ge,Vendor for Plant, Used to Account for Channel Bow ML20043B1021990-05-14014 May 1990 Responds to NRC 900412 Ltr Re Violations Noted in Insp Rept 50-333/90-01.Corrective Actions:Disciplinary Actions Taken & Job Performance Counseling Provided Re Responsibilites for Control Room Operations & Command in Control Room ML20043A7471990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-333/90-13.Util Requests That Notice of Violation Be Withdrawn & Reclassified as Deviation & That Submittal of Inaccurate Info Be Considered Isolated Case ML20042G8271990-05-0909 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Rept 50-333/90-11.Corrective Actions:Mod Error Corrected,New Transmitters Installed & Mod Procedures to Be Revised to Assign Responsibility for Calibr Points Value Calculation ML20042F3891990-04-30030 April 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20042E6251990-04-20020 April 1990 Forwards Application for Amend to License DPR-59,changing Tech Specs to Remove cycle-specific Parameter Limits & Ref Core Operating Limits Rept Which Contains Limits,Per Generic Ltr 88-16 ML20012F0361990-04-0505 April 1990 Forwards Temporary Addendum Rept for Rev 1 to Security Plan. Rept Withheld (Ref 10CFR73.21 & 2.790(d)(1)) ML20012F2161990-04-0202 April 1990 Forwards Application for Amend to License DPR-59,revising Sections 3.5.F & 4.5.F of Tech Specs, Min ECCS Availability. ML20012C9821990-03-13013 March 1990 Forwards Application for Amend to License DPR-59,changing Tech Spec Section 4.9.F, LPCI Motor-Operated Valve Independent Power Supplies, on Page 222a.Changes Purely Editorial in Nature & Revises Surveillance Requirement ML20012C0441990-03-0909 March 1990 Forwards Application for Amend to License DPR-59,clarifying Spec 3.9.B.3 Re Diesel Generator Operability to Eliminate Erroneous Ref to Both Diesel Generator Sys ML20012A1021990-03-0101 March 1990 Forwards Inservice Insp Hydrostatic Test Program for Class 2 & 3 Sys Conducted During First 10-Yr Insp Interval. Relief Requested for Second 10-yr Insp Interval for Hydrostatic Relief Requests Contained in Encl ML20012A0201990-02-28028 February 1990 Forwards Response to NRC SALP Initial Rept 50-333/88-99 for May 1988 - Sept 1989.Emergency Operating Procedures Being Upgraded to Rev 4 of Emergency Procedures Guidelines & Will Be in Place Upon Startup from Spring Refueling Outage ML20012A9301990-02-28028 February 1990 Forwards New York Power Authority Ja Fitzpatrick Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept Jul-Dec 1989 & Rev 7 to Odcm. JPN-90-016, Requests That 900209 Application for Amend to License DPR-59 Be Processed on Emergency Basis & Approved by 900225 to Avoid Premature Plant Shutdown1990-02-21021 February 1990 Requests That 900209 Application for Amend to License DPR-59 Be Processed on Emergency Basis & Approved by 900225 to Avoid Premature Plant Shutdown ML20006E3921990-02-13013 February 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Testing of Circulating Water/Svc Water Sys for Mussels Will Begin Spring 1990 ML20006E2681990-02-0909 February 1990 Forwards Application for Amend to License DPR-59,revising Tech Specs Re RHR Pump Operability ML20006E3321990-02-0808 February 1990 Notifies Second 10-yr Inservice Insp Interval Scheduled to End in Jul 1995 & Valve Insp During 1990,91 & 93 Refueling Outages ML20006C8271990-01-29029 January 1990 Responds to NRC 891229 Ltr Re Violations Noted in Insp Rept 50-333/89-21.Corrective Action:Background Instrumentation Results Will Be Reviewed on Periodic Basis ML20006C3811990-01-29029 January 1990 Forwards Preoutage IGSCC Insp Plan for Upcoming 1990 Refueling Outage.Util Will Not Routinely Submit Preoutage Plans in Future Per Generic Ltr 88-01 & NUREG-0313 ML20006A7771990-01-19019 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing-Check Valves or Valves of Similar Design. No Insp of Valves Performed ML19354E0341990-01-16016 January 1990 Forwards Application for Amend to License DPR-59,revising Tech Spec 4.11.B.2, Crescent Area Ventilation to Require Calibr of Existing Temp Indicator Controllers or New Temp Control Switches ML19354E0321990-01-16016 January 1990 Forwards Application for Amend to License DPR-59,revising Tech Spec Section 4.7.A.2 & Associated Bases Re Primary Containment Leak Rate Testing Requirements ML19354E0421990-01-16016 January 1990 Forwards Application for Amend to License DPR-59,revising Tech Specs Re Augmented Inservice Insp of Main Steam & Feedwater Piping Welds.Spec 4.6.F.2, Structural Integrity & Associated Bases on Pages 144 & 153 Deleted ML19354D8861990-01-12012 January 1990 Forwards Application for Amend to License DPR-59,modifing Tech Spec Table 3.7.1, Process Pipeline Primary Containment & Table 4.7.2, Exception to Type C Tests to Replace Traversing in-core Probe Sys ML19354D8701990-01-12012 January 1990 Forwards Application for Amend to License DPR-59,revising Note 16 to Table 3.1-1 & Note 9 to Table 3.2-1 to Increase Main Steam Line High Radiation Monitor Trip Level Setpoint During Operating Cycle 10 ML19354E0531990-01-12012 January 1990 Forwards Application for Amend to License DPR-59,revising Tech Spec 3.6.A, Pressurization & Thermal Limits, to Comply W/Generic Ltr 88-11 & Reg Guide 1.99,Rev 2 ML20005G7191990-01-12012 January 1990 Forwards Application for Amend to License DPR-59,revising Tech Spec Table 3.2-2, Instrumentation That Initiates or Controls Core & Containment Cooling Sys to Change Second Level Undervoltage Trip Setpoint for 1990 Refueling Outage ML20006A4021990-01-12012 January 1990 Forwards Application for Amend to License DPR-59,removing cycle-specific Parameter Limits from Tech Specs & Relocating Limits to Core Operating Limits Rept,Per Generic Ltr 88-16 ML20005G2671990-01-0909 January 1990 Forwards Application for Amend to License DPR-59,changing Safety Limit Min Critical Power Ratio from Current Value of 1.04 to 1.07 to Support Cycle 10 Reload Fuel Design 1990-09-07
[Table view] |
Text
. . . - , . - . - - - - _-..- - .------ . . . _ . - . _ . _ . - _ _ .- . --. _ - _ -
i .
Jzmas A. Fit:Pstriels l
Nuclett Powst Pl:nt l PO Bos 41 ,
( Lycoming. New York 13093 f 31$ 342.384o I l i l Radford J. Converse ;
~
! #D NewYorkPbwer tv Authority
~
May 29, 1987 JAFP-87-0441 i
United States Nuclear Regulatory Commission !
Document Control Desk Washington, DC 20555 i
Subject:
James A. FitzPatrick Nuc1 ar Power Plant !
Docket No. 50-333
. Cycle 8 Start-Up Testing Report Centlement Enclosed you will find the Cycle 8 Start-up Testing Report for the James A. >
FitzPatrick Nucicar Power Plant, which is submitted to you in accordance with Regulatory Guide 10.1 and Plant Technical Specifications paragraph 6.9.A.1, We trust you will find this information satisfactory. Ilowever, should you desire additionni information, please do not hesitate to contact Mr. David Burch at (315) 349-6311.
.- t ,
o~ .
RADFORD J. CONVERSE :
RJC admh Enclosure !
i CC: U.S. Nuclear Regulatory Commission Region 1. Attention: W.T. Russell, Regional Administrator NRC Resident Inspector .
WPO for RMS lleadquarters Distribution G. Rorke W. Fernandez l D. Burch R. Cliane Document Control Center pa87060 60387 03000,22870529 PDN 4y ,1 ,
l l
_. - - --_-- _~ . - - _ . -.- - . - - - . _ - - .- . _ _ . - - _-
t i
I i James A. FitzPaerick Cycle 8 Start-up Testing Report
?
1 j Cycle 8 on-line operations commenced April 30, 1987, ending a 105 day ,
! refueling outage. The start-up testing program was conducted from March 24, 1987 i through May 15, 1987 utilizing Reactor Analyst Procedure (RAP) 7.1.17. " Refueling j Start-up Program". i 1
Core Loading and Verification l Refueliig activities this outaga included a full core offload and reload. l During the riload three hundred and seventy-two irradiated assemblies and one ,
hundred and eighty-eight new fuel assemblies were loaded. Of these new j assemblies, tour were Westinghouse Lead Test Assemblies of the QUAD + design and f I the remaindet were General Electric GE8 fuel design. The finni loading map is -
- attached as Figure 1. ;
! Inverse multiplication plots were used throughout the fuel loading process j to monitor the subcriticality of the core. The final core loading was verified I in accordance with RAP-7.2.4, " Reactor Core Fuel Verification", using an :
j underwater television camera and recorder. This has been documented by QA Audit l 1 number 1170. '
i f Control Rod Drive Testat L l i i Prior to start-up, surveillance tests F-ST-23B, " Control Rod Coupling i Integrity Test" and F-ST-20K, "CRD Exercise / Venting Timing Test", were :
satisfactorily completed for all 137 control rods. Twenty control blades were l repinced during the outage.
Control rod scram time testing was conducted in accordance with RAP-7.3.10, i j " Control Rod Scram Time Evaluation", prior to reaching 40% rated core thermal ;
j power. The results were as follows: r
\l Notch Tech Spec Average of
! Observed Limit (acc) 137 rods (ace) i i !
j 46 .338 .321 i 38 .923 .741 l j 24 1.992 1.499 I
- 04 3.554 2.633 1
j The average time to notch 38 required the alternata method of determining r i the Minimum Crittent Power Itatio (MCPR) limit as outlined in Technical Specifica- i j tion 3.1.B.2. No adjustment to the MCPR limit was required at this point in the l' j cycle.
The average of the scram insertion times of the three fastest operable i control roda for all groups of four control rodn in a two by two array wore less !
than the maximum times allowed by the Technical Specittentions. l 1 ,
I i i i I l 1 of 4 !
i i
__ -i
l
. l l
l l
l Shutdown Margin Test:
Initial criticality for this fuel cycle was achieved on April 22, 1987.
At this time, shutdown margin was demonstrated using the insequence critical method. This test demonstrated a shutdown margin of 1.511% AK.
Reactivity Anomaly Check:
A comparison of the expected and actual control rod density was performed at 100% rated core thermal power and 99.3% rated core flow, in accordance with RAP-7.3.6, " Reactivity Follow". The actual control rod inventory was 456 notches inserted. This showed good agreement with the predicted inventory of 432 notches inserted. (2250 notches is equivalent to 11% AK)
Power Distribution Mensurements:
Core power distribution was monitored throughout the power ascension testing with the Traversing Incore Probo (TIP) System and Local Power Range Monitors (LPRM). LPRM calibrations were performed at 35%, 50% 75%, and 100% rated core thermal power. Reactor thermal limits were maintained within Technical Specification Limits.
Coro Power Symmetry:
Core power symmetry was checked at 50%, 75%, and 100% rated core thermal power. The maximum percent difference in power level of symmetrically located fuel bundles was found to be less than 10%.
LPRM Responne Tent During scram time testing, when control rod insertions and withdrawals were being modo, a LPRM renponse test was conducted on all 124 LPRM detectors. This verified neutron responne and demonstrated that the detectors were connected to their proper flux amplifiers. Twenty LPRM nonemblien were repInced during the outage.
, Prenmura Regulator T nt KAP-7.3.18. "Prennure Regulator Tents", was performed at 25% rated core thermal power. The doeny ratio of the responne to changes in the preneure regulator was verified to be less than 1.0. The take-over capability of the back-up pressure regulator was demonstrated during simulated failures of the controlling regulator.
Procann Computar Checkout:
The procons computer databank for Cycle H operation van installed and satisfactorily checked out over the time period of April 16-17, 1987. This work van performed by site pernonnel with the assistance of pornonnel from the General Electric Nuclear Data Hanks group in San June, CA.
2 of 4 1
I .
l Core Performance calculations were made at 35%, 50%, 75% and 100% rated core thermal power using manual, process computer, and the off-line Back-Up Core i Limits Evaluation methods. In each case, the power levels were in agreement.
l Values and core locations for Maximum Fraction of Limiting Critical Power Ratio I (MFLCPR), Maximum Fraction of Limiting Power Density (MFLPD), and Maximum Average l Planar linear heat generation ratio to limits (MAPRAT) determined by BUCLE agreed j closely with the plant process computer calculations.
TIP Axial Alignment and System Checkout:
Since some TIP tubing was replaced, tests to verify the proper alignment and operation of the TIP System were performed in accordance with F-IMP-7.26 and RAP-7.3.14. Some adjustments were required to make the system operate correctly for the OD-1 Whole Core LPRM Calibration and Base Distribution computer program.
TIP System Uncertainty Test:
The TIP Reading uncertainty was determined to be 5.776% from a comparison of symmetric LPRM string Base distributions taken at 100% rated core thermal power.
Using the annumed uncertainty values of 3.4% for LPRM extrapolation and 3.7% for TIP Software modeling, the total TIP System uncertainty was determined to be 7.66%. This is below the 8.7% value assumed in the Licensing Topical Report and is, therefore, satisfactory.
Core Flow Evaluation:
RAP-7.3.7, " Core Flow Evaluation and Indication Calibration", was performed at 85% rated core thermal power with results showing a .92% difference between indicated flow and calculated. This was within the 22.5% required by the procedure and assumed for the statistical uncertainty in the Licensing Topical Report.
At 100% rated core thermal power and 100% rated core flow by indication, another evaluation was performed. Again, the results were within the 12.5%
criterion. Closer inspection of the data revealed, however, that the output from
) the flow summer 02-3-SUH-/5D was reading low. Instrument and Control Department corrected the flow nummer problem and adjusted the output of the proportional amplifiera 02-3-PA-76A and 768 to make the final indicated flow read closer to the calculated value.
A third core flow evaluation was performed at 100% rated core thermal power and 98% rated core flow by indication. Results showed the difference between indicated and calculated to be 1.65%. One final adjustment was made to lower the indicated flow to match the calculated value of 97% rated core flow.
.Dotermination of Hated Driva Flowl In conjunction with the core flow avaluations, data was obtained to determino ['ated recirculation drive flow. This flow was calculated to be 33.34 x 10 lb/hr.
3 of 4 m
- l i . .
1 i
Core thermal liydraulic Stability: j li 1 Data from the APRMs and the A and C level detectors of one LPRM in each ,
r octant was acquired in accordance with F-ST-5S. " Neutron Instrumentation Noise ;
j Monitoring", at 35% and 75% rated core thermal power. This information will j serve as baseline data for the operating cycle it, and when Technical ;
i Specifications require performance of F-ST-55. l
) i
- other Tests
- !
l Y Various surveillance tests were satisfactorily completed as required by {
i' RAP-7.1.17 and F-0P-65. i l
Because one of the low pressure turbines was replaced during the outage. l i extensive testing was performed on the turbine generator. This included a I
! torsional test, overspeed tests, and vibration tests. All were completed l satisfactorily, l
i
[
i i l 1 !
I f 1 l i
i I
1 !
+
I r
! l
! I i !
i l I 1
l i >
i t i !
I i
1 I 4 of 4 ;
i 5
4 :
1
' 1 i i '
2 e 3 e , ,
e, M w I et o e r e e, ,e , I es g e , g
, , t r . : r e I
% *4, 9 , t
- f . g e es e= , 4 e e i ae a u, as t, ao a e, e n an ao s s tt t ss t n e, a t e, 1 - s s sm i
l ; -
r r'; , 'r
. e e, vs w we wt we ea ea ve t Al e, ae ne an te as st ao st as se mee, ar te sv t e w e, a
si a
t.
ae l6 s t s ,
wa a, Te e e ,
eo n ,,, n e< sm i
e, e t wr as v, a ae n e, e e, sS ae a a ar a, ns at a e, it as ae
- s e la t n e, n .s n e, t. ie ai se nf il dm s
t e r' r L
, It r r -1 n, rt _
we vs er vS su u s, n e,
, e, n ,, em n
ee nts e
ao ee nne su a as te sz ae as nse ie oe as use ea sn ss au e-n at
)o nr s at te a
is as ts ts ie n e ts ie e
g s, es s. s ei ae wS em e e, t .,
a s u, n ,,
e, .
n o., e.
n.
st oto v.
a.
n.
ae nr a t
i 0 da 4, t 9 nte a t
n,,e i
st a s ie as nee an to s
am i
an io as nt ae te nr e as a s at ne x,
x rj it r 'r It N'.
I e
r nt o 1 e*
u
, w s, e, au e a* n u w se we aa n 9 9w v e, as e, as me en nt o e, o e, ao ie a,,
t a
tt as lt nss s e, i
n.
si an a
ao s
a8 i%
4 1e ne a t **
ie S es se es a s ec a en am ee eo s, ss e ee s
- a. e, as s. es se aa ar ae M aa a
vg aa nn ae t s ne ne no nse n a a g , an t
ae ie a t
s, nt n ,. se i6 a e ns n o, au i 1e ne tt i: n s
' n m
~
v;
' i.
I rt r
r L
- r g
- r ee e a
( .
se <+
u v s er at e< ee s e to e.e s ees e eg a g es .,
vf ai a c, si e, at w aw as nu au ae so at ne s* ss te a =
to nse a e, t
af it m. e.n. u.e e nt a t
e, t , e nt t n s, si io te te ls te te
. t se eg eh e s ne M ae wt a, et a a
_* 1 eG ee e, se eu s, so as es ae a, ae aw ne ew a ar st ss te a
tn ar te is nos a t e,
_E a e, 9
a5 a6 n,e m e.m o.ote a
t.
a, t , a~n.ia so is nso i. aM i nt te ie ia t t 3 t *
- 'm H . l It g 'L r'.i -r r[
1, l -
m x ~
s u
Z en o- e s e
e s ee es r ss ao ae i
ao t.
- a. ae ue na s
nee a t e, 3
e w%
a 7
te **8 t
ee
- n. s e.
ne n, oo. sa s.
I, f ,
ss s.
ea n ,= sa e* ae ss n o, n e*
a*
s4 se e s Im i l , is is ie tg 3 e, nke s$ t e B" , ie e s e
as es ee e n e se n a' a, ee se s sa ae a
ea es eee .m
- a s sw aw ae a am a ,e as as ao s, aa se am a
n . t s9 n,m te se a
- t E f ie at ti ns ne mM ee e.
n.
s s,
ae s -
a ts s e, i
a n e um n s+ nW n t t i e n
,J j
m_ , r r p
- l y t
>T r[ m
-y e,l , 1 yn -_ _
f 4 e* 3
sara ea ae aa *
% s ,
ss we
- 3 sd ee as a a a,, a n u, t
- ae a a r m.e e ane n" s- nre ac sM i to se mUS tt m.. m- nn sm a ie t
- ae ae ae ne e s i, ta sa ss t ' i l t l
_ +
9 se as e. e .S n e, 1 . iIs6 ae 9s v
a-e ms ae s" a ae w
s-a ae r
e e*
n **
ae s'
er Me 1a es se te a
sm t
oe nJ E ae t '
l 4 I
3 M ae t,*, _i ae l e l
t ,m a=
l l
ne
,i jI i* t
1 j j E
rj rL r t re b r
e' i . - a s ,e 4 .* s* eS ee es e
" D
- n. .s
_ we e e e w4 en n a=
t ea e= e no,u.se s ae a \, n e, em a aa a m, n- no
- e. **
nn mm ao ae s i e, a e e ae se ao s L tast n J t e ss ss4 s s t n .* e ts s r t e ne t e ,s st u
' kb4 s
i;
, a b a.
I J
pc sn ev
= ee ae ea '
_s e m
we ee .e e. e. e ee a, ae s
sn n ae sg nw ms e ee se ae aas na a=
aa an sc e
- a. as ar ses ae ot a
as t e sas t n e= n o- n e. no 4
. e, ne. l, a n s. so a e e ts n' s ia t u n, te y
s =
,, J ' 'j - ,
'; j u n
, I
, ; 1 r,j F l,
u IL e ".
' I ;
- " e .
i
.s ug n e aan e, ea s es ee se us ee e e e e* s sf 4e ss e e a e. aom n<. sn g o ,. r na, g
. s 1t nm .~
o ne- .u n- a td a n s, t e
- so e e ao s a t
,a a s o, n ** nse au u t i , oee nb I
Ii la, s r g s
e n ,e .u n6s e e, s,
2g n ,, e e.
- n. a e, e sl ae a n e , t
- ma ss e_aa n en e, as ms ae u
st ie 1 e * .a e ie t ws vs
- n. mea r se i* as e-n n aa te a
a nre sa i g
gr at na ,a ee s*
7j ,
x, ,, ,
7 o ajl:
i"i!IiIl 1
- ,l rg F - &f ro i 3 t , "h -
e e og ,.o e, g
ea em m- an**- a*
a ea et es ..e e* ea e s sa s as e. t eo s. . '
s- am s o ae zr e. ,e, 8 ae g s e,
n1 sa t d n. ne n *. nge sm t
a iw d,
1.
ao is ae t
- s t n* u e ne t ne nne ts e
i2 na e i*
- I
, s . ag a a.
a es es am o e. es ne e er ms e. ese ee eee .e so "
g3 a%
3 p
6 e 3 e m . m.. me s e na s ss ,,
t e ae ts ia nes n. are t e s e te l g
e s .e ae t = ne as t e nn ,n as ia nm d^
,<j.i*,jlfgl .
. I t
jaygj, y, ,,
Ti _gg5a l. 7 Rg e _ -
e e
ag
- e. ee es e a
s, s es ee e
me s aes e
ee si au e ,, e, s
E i= n.e m =*.s.e. n6e t a ,
t , ie s
t e n* e n m.- aa s no a e. e=
n ss te a
i ,t t
,e s.
i.
3-#
{t g ,
M,
.Il s i m o
. , == = e-u e, ez st n e s e e= g a
f a>s s
- n. nm ne a t
,, nu ae n
a*
ae s
es nee sne i*
ee nu e.
e.
se t s sn i
e ae uen es nes e
ys a i
o, " /n jsT
- j ,j Y T,;4 A9 +ls. y rj_ ,gl
3 ,j T1 ygT ,l ya .g e
,- er _
ag a e.. es ee e, em sr ae e.
m e
- n. mou nee ss a ae s9 ,ces w **
,.es tg i, t,, s. i. t e eu ae et e. sn e oe ee ae m _enne us ao t o nee ae io m g. nse a ser t s sg a . ,i ji i- ,i jl:
_li +pj <1
. _ ij. l
- n. .e
.S e e, s. si a e ea 4
_a 5 ,m .n e~
a e, a e e.
s eo ee sI es ao e. ta eu ea e
. e. i + ' , t e ag a n s nen e :
i2 se nu na aw ns ag ue noe nm v ,j;yy gg ;f3ij,lgT _
g g ti ag,,f_l7 t s
,l-i a!';4yTg,
- - o ee
- T . -
e n ee e, e es e ne- o.m oe= n..
,e
- e. 2n ee a,
+e a n e. e. -
gl:lg4j j n%
s e s ea 2
nse 1w s .e er ie ne n, n. a a s.
se i*
a m
lI; i
a; : - !j_
a S. e, ee cm ee ee e
- n ,, s- ae es ss mo ea ee e s a
n e. ae m e-an n- a.
6 n e so
te is nes t . .
e e s
-lay e ti l,gl
_l ,,l _
S. n
_ .o8 si e. ae s a, o .
- y t ,
eFj t =
.j, ,
awsw"n, s . i-n*w nee a e.
s m
a-s
- l #;
gi l 1
- Illa 1 q 1. l