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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] |
Text
- . m - .. _ _ _ - .. 2 _
e-123 Main street WNte Plains. New York 10601
.p 914 681 6200
- > NewYorkPower 4v Authority
- November 4,1994 JPN-94-057 U, S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Safety-Related Motor-Operated Valve Testing and Surveillance Program (Generic Letter 89-10)
BegueELfoLSchedulehtension
REFERENCES:
- 1. NRC Generic Letter 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," dated June 28,1989.
- 2. NRC Generic Letter 8910, Supplement 6, "Information on Schedule and Grouping, and Staff Responses to Additional Public Questions," dated March 8,1994.
Dear Sir:
This letter requests a six month extension to the original schedule commitment for the completion of the FitzPatrick Generic Letter 89-10 program (Reference 1). The original j schedule commitment is the third refueling outage after Generic Letter 89-10 was issued. The
- extension is needed to complete the documentation and evaluation of the testing and valve !
modifications being performed during the third refueling outage, which is scheduled to begin l November 1994. ,
, I The Authority has completed the review of design basis system parameters and initial l static testing for the 91 valves currently in the program. Dynamic testing will be completed during the startup period following the upcoming refueling outage. Valves which cannot be verified by dynamic testing will be setup based on current best available information, within the original commitment schedule.
9411080162 9411'A ~5 PDR _ADOCK 0500 ,
P \ .
i Attachment i provides supporting information specified in Generic Letter 89-10, Supplement 6 (Reference 2) to justify this schedule extension request. Attachment il provides additionalinformation regarding analysis methods, as requested by the NRC staff during a telephone call with the Authority on October 13,1994.
ll you have any questions, please contact Mr. J. A. Gray, Jr.
Very truly yours, William J. Cahill, Jr.
l; Executive Vice President and Chief Nuclear Officer l l
)
STATE OF NEW YORK l COUNTY OF WESTCHESTER Subscribed and sworn to before me KATHLEEN D GALLAGHER this Y - 4 Notary Pu c. New York day of November 1994.
Qualified in Westchester count Commission Expires Nov.16,1 b -
P Notary Public / /
cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 Mr. John E. Menning Project Manager )
Project Directorate I-1 Division of Reactor Projects - t/II '
U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555
. l ATTACHMENT l TO JPN-94-057 MOV PROGRAM COMPLETION STATUS AND CAPABILITY OF VALVES NOT VERIFIED BY DYNAMIC TESTING Page 1 of 4 This attachment provides supporting information for a six month extension of the Generic ;
Letter 89-10 MOV program (Reference 1) at the James A. FitzPatrick Nuclear Power Plant.
The original schedule commitment is the third refueling outage after Generic Letter 89-10 was
~ issued. The extension is needed to complete the documentation and evaluation of the testing -
and valve modifications being performed during the third refueling outage, which is scheduled >
to begin November 1994.
The following information is provided based on guidance from the NRC for schedule extension requests (Reference 2): :
A. PROGRAM COMPLETION STATUS The Authority has completed the review of design basis system parameters and initial static testing for the 91 valves currently in the program. The Authrity has completed dynamic testing of 30 valves. Dynamic tests are scheduled for an a litional 16 valves during the ,
upcoming refueling outage (RFO) and the startup period following the outage. Initial reviews of DP test results, with linear extrapolation to design basis differential pressure, will be performed before the valves are returned to service.
The Authority has determined that 46 of the 91 valves currently in the program can not be verified by dynamic testing. Evaluations of the design basis capability of these non-testable '
valves are complete and 38 valves are currently setup based on best available information.
The remaining 8 valves are scheduled for modification or adjustment during the RFO. These ,
valves will be setup based on best available information within the original commitment !
schedule. Additional information regarding the definitions for non-testable valves and the analysis methods used to evaluate these valves is provided in Section B. :
B. DATA AND CAPABILITY EVALUATION FOR VALVES NOT DYNAMICAL'L Y TESTED Rafioitloos_.ancLClassincatina A valve in the MOV program is not dynamically tested if it is 'Not Practicable to Test' (NPT) or
'Not Meaningful to Test' (NMT). A valve is not practicable to test if that test:
- will violate a Technical Specification,
- has the potential to damage station equipment, a requires modification of existing plant equipment, or a requires systems lineups which would result in a safety concem or an unresolved safety issue.
1
-. _ ~ _ - .. . .-- -- .
1 ATTACHMENT I TO JPN-94-057 MOV PROGRAM COMPLETION STATUS AND CAPABILITY OF VALVES NOT VERIFIED BY DYNAMIC TESTING Page 2 of 4 NMT means that the valve could be tested, but that test would not provide significant new information. Dynamic testing is not meaningfulif any of the following conditions apply:
i e The differential pressure (DP) thrust component of the total thrust requirement is less than or equal to 10% of the total thrust requirement, for gate and globe valves. ;
- The aerodynamic torque is less than or equal to 10% of the total torque requirement, for butterfly valves.
- The MOV is a globe valve with an open safety function, which is pressure or flow assisted in the open direction, and which has the torque switch bypassed in the DP loading region of the open stroke.
- The margin between MOV thrust capability (or torque for butterfly valves) at the ]
current field settings and the required thrust (or torque) determined from engineering analyses is at least 100%. This margin is above that already i incorporated for torque switch repeatability, rate of loading, and diagnostic test l equipment inaccuracy. '
Safety _Eunctions oLValves NRLDynamically Tested Table One provides safety function data for the 46 valves in the FitzPatrick program which are NPT or NMT. This table identifies the valve number, system function, and the safety function ,
in the open, close, or both directions. The table also provides a measure of the relative risk i significance for each of the 46 valves. The FitzPatrick Individual Plant Examination (IPE) model was used to develop this information.
Risk significance is a quantitative measure of the effect of a single MOV or group of MOVs on the core damage frequency (CDF) in the IPE Level I analysis and on the radiological release frequency (RRF) in the Level ll analysis. The evaluation performed to determine the risk ,
significance of the FitzPatrick MOV program valves was based on the guidelines of NUMARC l 93-05 (Reference 3). The MOV's were placed into one of three risk significance ranking ;
categories based on the following criteria: l l
High Equivalent to a 50% or greater increase in the total baseline core damage frequency.
Medium Equivalent to a 10% to 50% increase in the total baseline core damage frequency Low Equivalent to less than a 10% increase in the total baseline core damage frequency.
. . ~ . -
ATTACHMENT 1 TO JPN-94-057 MOV PROGRAM COMPLETION STATUS AND CAPABILITY OF VALVES NOT VERIFIED BY DYNAMIC TESTING Page 3 of 4 EYaluation Methodology for ValvasERLRynamically Tested Evaluations were performed for each of the valves not dynamically tested to establish thrust target widows for setting up the valves and to identify the need for modifications. The evaluations were based on best available industry and plant specific data, including use of conservative assumptions where specific data was not available.
The evaluation methodology consists of three parts.
- Calculate the minimum stem thrust requirement for design basis flow and r differential pressure conditions.
- Calculate the maximum stern thrust and torque limitations based on motor capability, spring pack limitations, and valve and actuator weak link analysis.
- Apply margin to the calculated thrust and torque values to account for torque switch repeatability (TSR) and diagnostic test equipment inaccuracy. Margin for rate of loading (ROL) is also applied to the minimum stem thrust requirement.
The analysis method used to calculate thrust and torque is described in Attachment II. Values for margin are determined as follows.
The margin for TSR is based on guidance from the valve actuator manufacturer, Umitorque (Reference 4), unless lower values can be justified using site empirical data.
VOTES equipment is used at FitzPatrick and margin for inaccuracy is applied based on vendor recommendations. The Authority previously provided information (Reference 5) to the l NRC on this subject in response to Supplement 5 (Reference 6). ,
ROL is defined as the difference between an MOV's control switch trip (CST) thrust output ,
under static and dynamic conditions. When this difference is greater than the square root of the sum of the squares of diagnostic equipment inaccuracy and TSR, the difference is !
considered to be ROL.
Margin for the combined effects of TSR, ROL, and diagnostic equipment inaccuracy is applied to the minimum required thrust. A bias ROL value, which is added directly to the minimum required thrust, is determined by calculating the ROL mean for the site DP test population. A random ROL value is determined by calculating the ROL standard deviar on for the site DP test population. The random ROL value is added to the TSR and diagt.astic equipment ,
inaccuracy values using the square root of the sum of the squares method. The resulting sum is applied to the minimum required thrust.
Margin for the combined effects of diagnostic equipment inaccuracy and TSR is applied to the !
maximum allowable thrust and torque. The margin value is obtained by combining diagnostic equipment inaccuracy and TSR using the square root of the sum of the squares method.
l i
ATTACHMENT I TO JPN-94-057 MOV PROGRAM COMPLETlON STATUS AND CAPABILITY OF VALVES NOT VERIFIED BY DYNAMIC TESTING Page 4 of 4 EyalualiGDRCSults The results of the evaluations for the valves not dynamically tested are reported in Table Two.
This table identifies the valve number, valve type and size, and design basis differential pressure and flow rate. Thrust margin and available valve factor are reported in the table to provide quantitative measures of valve capability. The evaluation results include the effects of modifications or adjustments previously performed to improve design basis capability and available margin.
Eight of these valves are scheduled for modification or adjustment during the RFO. These valves will be setup to meet their minimum thrust requirement with margin for torque switch repeatability, diagnostic equipment inaccuracy, and rate of loading, by the original commitrnent date for program completion.
C. REFERENCES
- 1. NRC Generic Letter 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," dated June 28,1989.
- 2. NRC Generic Letter 89-10, Supplement 6, "Information on Schedule and Grouping, and Staff Responses to Additional Public Questions," dated March 8,1994.
- 3. NUMARC 93-05, " Guidelines for Optimizing Safety Benefits in Assuring the ,
Performance of Motor-Operated Valves," Nuclear Management and Resources Council, Inc., dated December,1993.
- 4. Limitorque Maintenance Update 92-2, regarding various technical aspects of l Limitorque motor operators.
- 5. NYPA letter (JPN-93-072/ IPN-93-115), R. E. Beedle to NRC, " Response to Generic Letter 89-10, Supplement 5," dated September 30,1993. ;
1
- 6. NRC Generic Letter 89-10, Supplement 5, " Inaccuracy of Motor-Operated Valve l Diagnostic Equipment," dated June 28,1993.
l l
l i
. TABLE ONE MOV SAFETY FUNCTION DATA FOR VALVES NOT VERIFIED BY DYNAMIC TESTING (Page 1 Of 2)
SAFETY FUNCTION **
MOV ID RISK VALVE DESCRIPTION OPEN CLOSE CAT.
02MOV-53A Low RECIRC PUMP A DISCHARGE N/A LPCI initiation 02MOV-538 Low RECIRC PUMP B DISCHARGE N/A LPCI initiation 10MOV-17 High RHR SHUTDOWN COOLING OUTBD N/A Containment Isolation 10MOV 18 High RHR SHUTDOWN COOLING INBD N/A Containment Isolation 10MOV-26A High RHR A CONTAINMT SPRAY OUTBD Initiate Drywell Sprays Containment Isolation 10MOV-26B High RHR B CONTAINMT SPRAY OUTBD Initiate Drywell Sprays Cor tainment isolation -
10MOV-31 A High RHR A CONTAINMENT SPRAY INBD Initiate Drywell Sprays Containment Isolation 10MOV-31 B High RHR B CONTAINMENT SPRAY INBD Initiate Drywell Sprays Containment Isolation l 12MOV-15 Low RWCU SUPPLY INBD N/A Containment Isolation 12MOV 18 Low RWCU SUPPLY OUTBD N/A Containment Isolation t I
12MOV-69 Low RWCU RETURN N/A Containment isolation ,
13MOV-15 Low RCIC STEAM SUPPLY INBD N/A Containment Isolation '
13MOV-18 Low RCIC PUMP SUCTION FROM CST N/A Suction transfer to Torus 13MOV 21 Med RCIC PUMP DISCHARGE INBD RCIC initiation Containment Isolation 13MOV-39 Med RCIC PUMP SUCT FM TORUS OUTBD Align RCIC Suction to Containment Isolation Torus 13MOV-41 Med RCIC PUMP SUCT FM TORUS INBD Align RCIC Suction to Containment Isolation Torus 13MOV 132 Med RCIC TURBINE LUBE OIL CLG WTR RCIC Turbine Lube Oil N/A Cooling 14MOV-7A Low CSP PUMP A TORUS SUCTION N/A Containment Isolation 14MOV-7B Low CSP PUMP B TORUS SUCTION N/A Containment Isolation 14MOV-11 A Low CSP A DISCHARGE INJECTION OTBD N/A Containment Isolation 14MOV-11B Low CSP B DISCHARGE INJECTION OTBD N/A Containment Isolation 15MOV-175A Low RBCLC/ESW CROSSTIE RETURN ESW to Supply RBCLC Terminate ESW Supply 15MOV 175B Low RBCLC/ESW CROSSTIE RETURN ESW to Supply RBCLC Terminate ESW Supply 20MOV-94 Low DW EQUlP DRAIN SUMP DISCHARGE N/A Containment Isolation 23MOV 15 Low HPCI STEAM SUPPLY INBD N/A Containment Isolation 23MOV-17 Low HPCI PUMP SUCTION FROM CST N/A HPCI Suction transfer to Torus 1
i
TABLE ONE MOV SAFETY FUNCTION DATA FOR VALVES NOT VERIFIED BY DYNAMIC TESTING (Page 2 of 2) i SAFETY FUNCTION **
MOV ID RISK VALVE DESCRIPTION OPEN CLOSE CAT.
23MOV 19 High HPCI PUMP DISCHARGE INBD HPCl initiation Containment Isolation 23MOV 57 High HPCI PMP SUCT FROM TORUS OTBD Align Suction to Torus Containment Isolation 23MOV-58 High HPCI PMP SUCT FROM TORUS INBD Align Suction to Torus Containment Isolation 27MOV 113 Low CAD DRYWELL EXHAUST BYP OTBD Direct Contain gases to Containment Isolation SGT 23MOV 117 Low CAD TORUS EXHAUST BYPASS INBD Direct Contain gases to Containment isolation SGT 27MOV-120 Low CAD CONTAIN EXHAUST TO SGT Direct Contain gases to N/A SGT 27MOV 121 Low CAD CONTAIN EXHAUST TO SGT Direct Contain gases to N/A SGT 27MOV 122 Low CAD DRYWELL EXHAUST BYP INBD Direct Contain gases to Containment isolation SGT 27MOV-123 Low CAD TORUS EXHAUST BYP OUTBD Direct Contain gases to Containment Isolation SGT 29MOV 74 Low MST INSIDE STEAM DRAIN N/A Containment isolation 29MOV-200A Low MSLCS A MASTER ISOLATION Collect MSIV Leakage N/A 29MOV-2008 Low MSLCS B MASTER ISOLATION Collect MSIV Leakage N/A 29MOV-201 A Low MSLCS/SGT A ISOLATION Collect MSIV Leakage High Pressure to SGT 29MOV 201B Low MSLCS/SGT B ISOLATION Collect MSIV Leakage High Pressure to SGT 29MOV-202A Low MSLCS/SGT EVU ISOLATION N/A High Pressure to SGT 29MOV 202B Low MSLCS/SGT B/U ISOLATION N/A High Pressure to SGT 29MOV 203A Low MSLCS A MSIV LEAKOFF Collect MSIV Packing N/A Leakage 29MOV-203B Low MSLCS B MSIV LEAKOFF Collect MSIV Packing N/A Leakage 25,MOV-204A Low MSLCS A BYPASS DRAIN N/A Collect MSIV Leakage 29MOV 204B Low MSLCS B BYPASS DRAIN N/A Collec. MSIV Leakage
- N/A indicates that the valve dOes not need to Stroke to that position (Open or Closed) to perform a Safety function.
TABLE TWO -
DESIGN BASIS CAPABILITY FOR ;
VALVES NOT VERIFIED BY DYNAMIC TESTING !
(Page 1 of 4)
I MOV VALVE VALVE FLOW MAX DP AVAILABLE THRUST l lD TYPE SIZE RATE psid VALVE FACTOR MARGIN 02MOV-53A Parallel 28 see note B 200 0.71 32 %
[
Dbl Disc t
02MOV-53B Parallel 28 see note B 200 0.64 19% ;
Dbl Disc !
i 10MOV-17 Parallel 20 15400 gpm 97.8 0.77 28 % i Dbl Disc i a -
10MOV-18 Parallel 20 15400 gpm 100 see note D see note D j Dbl Disc ;
10MOV-26A Parallel 10 7200 gpm 242 see note D see note D Dbl Disc (217) (0.96) (82%)
10MOV-26B Parallel 10 7200 gpm 242 see note D see note D :
Dbl Disc (217f (0.92) (75%) j i
10MOV-31 A Globe 10 7200 gpm 239 2.44 103 %
(216) (2.47) (189%)
10MOV-31B Globe 10 7200 gpm 240 2.04 72 % l (216) (2.56) (198%)
12MOV-15 Parallel 6 1320 1103 see note D see note D Dbl Disc lbm/sec l 12MOV-18 Parallel 6 1320 1096 see note D see note D '
Dbl Disc lbm/sec i
12MOV-69 Parallel 4 600 1149 0.72 27 %
Dbl Disc lbm/sec 1 13MOV-15 Parallel 3 see note B 1090 see note D see note D Dbl Disc 1 13MOV-18 Solid wedge 6 416 gpm 21 3.4 71 %
13MOV-21 Flexible 4 see note B 1228 5.86 112 %
wedge (1228) (0.55) (10%)
(REFER TO NOTES ON PAGE 4) l
,-m. y -
e--
. i TABLE TWO DESIGN BASIS CAPABILITY FOR ,
VALVES NOT VERIFIED BY DYNAMIC TESTING (Page 2 of 4)
MOV VALVE VALVE FLOW MAX DP AVAILABLE THRUST '
ID TYPE SIZE RATE psid VALVE FACTOR MARGIN 13MOV--39 Solid wedge 6 see note B 34 2.64 95 %
(14) (16.04) (409%)
13MOV-41 Solid wedge 6 see note B 33 2.35 78 %
(13) (14.36) (348%)
13MOV-132 Globe 2 16 gpm (1160) (8.22) (2332 %)
14MOV-7A Solid wedge 16 see note B 33 2.22 175 %
14MOV-7B Solid wedge 16 see note B 33 1.84 135%
14MOV-11 A Flexible 10 6900 gpm 315 2.19 217 % i wedge )
14MOV-11B Flexible 10 6900 gpm 315 1.26 93 %
wedge 15MOV-175A Solid Wedge 6 2170 gpm 121 0.73 11 %
(108) (1.81) (138%) ;
15MOV-175B Solid Wedge 6 2170 gpm 120 0.86 25%
(107) (1.96) (154%)
1 20MOV-94 Parallel 3 100 gpm 79 4.93 146 % !
Dbl Disc l
23MOV-15 Parallel 10 see noto B 1090 see note D see note D Dbl Disc 23MOV-17 Solid wedge 16 4250 gpm 15 3.41 190 %
23MOV-19 Flexible 14 see note B 1181 1.31 110 %
wedge (1126) (0.66) (33%)
23MOV-57 Solid wedge 16 4250 gpm 37 1.25 77 %
(11) (3.88) (195%)
g it!MOV-58 Solid wedge 16 4250 gpm 37 0.91 34 %
(11) (2.69) (126%)
27MOV 113 Butterfly 3 see note B 44 see note C see note C (44) 27MOV-117 Butterfly 3 see note B 44 see note C see note C (44) {
l (REFER TO NOTES ON PAGE 4) l i
~
TABLE TWO l DESIGN BASIS CAPABILITY FOR j VALVES NOT VERIFIED BY DYNAMIC TESTING ;
(Page 3 of 4) !
.l, MOV VALVE VALVE FLOW MAX DP AVAILABLE THRUST l lD TYPE SIZE RATE psid VALVE FACTOR MARGIN 27MOV-120 Butterfly 12 see note B 0 see note C see note C 27MOV-121 Butterfly 6 see note B 2.2 see note C see note C l 27MOV-122 y-Globe 3 see note B 44 25.7 400 % :
(44) (78.22) (2224 %) j 27MOV-123 y-Globe 3 see note B 44 36.65 597 %
l (44) (72.49) (2063 %) !
29MOV-74 Parallel 3 see note B 1105 see note D see noto D l Dbl Disc 29MOV-200A y-Globe 1 see note B (1090) (18.66) (2952 %)
29MOV-2008 y-Globe 1 see note B (1090) (18.66) (2952 %) {
29MOV-201 A y-Globe 1 see note B 1 3402 244 % l (16) (919) (1172 %) l 29MOV-2018 y Globe 1 see note B 1 3933 285% ,
(16) (917) (1170 %) l 29MOV-202A y-Globe 1 see note B 16 220 251 %
i 29MOV-2028 y-Globe 1 see note B 16 213 242 %
i 4
29MOV-203A y Globe 1 see note B (1090) (13.53) (21476 %)
c 1
29MOV-2038 y-Globe 1 see note B (1090) (13.45) (21367 %) l 29MOV-204A y-Globe 1 see note B 16 179 199 %
} 29MOV-204B y-Globe 1 see note B 16 242 278 %
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, (REFER TO NOTES ON PAGE 4) e i
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TABLE TWO DESIGN BASIS CAPABILITY FOR -
VALVES NOT VERIFIED BY DYNAMIC TESTING
' (Page 4 of 4) r NOTES ,
A. ' Values in parentheses (xxx) are for the~ valve opening cc.2ditions. Otherwise, values are for valve closing. Data is provided for the valve position which corresponds to a safety function ;
as shown in Table One. Data is provided for valve opening and closing if the valve has safety .
functions in both positions. .
B. For cases where no flowrate is specified, the valve design basis DP condition does not include flow, or the original design basis review concluded that flowrate has no significant effect on the calculated MOV thrust requirement. ,
f C. Valve factors, minimum thrust requirements, thrust margins, stem coefficients of friction, etc, j are not applicable to butterfly valves. These valves will be setup, by the original commitment date for the FitzPatrick MOV program, using best available information including guidance .
provided in Information Notice 94-69, " Potential Inadequacies in the Prediction of Torque !
Requirements for and Torque Output of Motor-Operated Butterfly Valves."
D. These eight valves are scheduled for modification or adjustment during the 1994 refueling outage, to increase thrust margin. These valves will be setup to meet their minimum thrust requirement with margin for torque switch repeatability, diagnostic equipment inaccuracy, rate of loading, and stem lubrication degradation by the original commitment date for program completion.
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ATTACHMENT 11 TO JPN-94-057 TORQUE AND THRUST CALCULATION METHOD FOR GATE AND GLOBE MOTOR OPERATED VALVES (Page 1 of 5)
- 1. MWIMUM REQUJHED_TBRUST FOR GATE VALVES l Minimum required thrust (MNRT) to operate a motor operated gate valve against a differential pressure is: l MNRT = PL + PE + DPE where PL = packing load - Ibs .
PE = stem ejection force - Ibs DPE = differential pressure effect - Ibs PL is obtained from test data or industry standards. 4 PE is determined as follows:
PE = SA x LP where i SA = Stem cross sectional area at packing - in LP = Upstream line pressure - psig ]
PE is negative for opening stroke and positive for closing stroke.
DPE is determined as follows:
DPE = VF x AS x DP where AS = disc area based on mean seat contact diameter - in
. DP = differential pressure across valve seat - psi VF = valve factor - dimensionless (refer to next section for additional l discussion of valve factor) l 1
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ATTACHMENT ll TO JPN-94-057 TORQUE AND THRUST CALCULATION METHOD FOR GATE AND GLOBE MOTOR OPERATED VALVES (Page 2 of 5)
II. MINIMUM BEQUlBEDJ11 RUST FOR GLOBE _ VALVES Minimum required thrust (MNRT) to operate a motor operated globe valve against differential pressure is determined as follows:
STROKE FLOW MNRT DIRECTION DIRECTION CLOSE OVER SEAT PL + PE - DPE CLOSE UNDER SEAT PL + PE + DPE OPEN OVER SEAT PL - PE + DPE OPEN UNDER SEAT PL - PE - DPE PE is determined as follows:
STROKE FLOW PE DIRECTION DIRECTION CLOSE OVER SEAT SA X LP CLOSE UNDER SEAT (LP - DP) X SA OPEN OVER SEAT SA X LP OPEN UNDER SEAT (LP - DP) X SA DPE is determined as follows:
DPE = VF x AS x DP where VF and DP are as defined in the previous section. 'AS' in this case is the valve seat or guide area, as appropriate. Valve factors for valves that are Not Practicable to Test (NPT) or Not Meaningful to Test (NMT), are established using grouping techniques. Each of the valves in the program have been assigned to one of 16 defined groups, based on valve type and manufacturer. There are 8 groups of globe valves,7 groups of gate valves, and all butterfly valves are in one group.
The empirical valve factor data for testable valves in the group is used for the non-testable valves in the same group. Statistical analysis is used to establish the appropriate valve f actor for the group.
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l ATTACHMENT ll TO JPN-94-XXX TORQUE AND THRUST CALCULATION METHOD FOR GATE AND GLOBE MOTOR OPERATED VALVES (Page 3 of 5) 111. STEM FACTOR The stem factor (SF) is a conversion factor used to convert actuator output torque to stem thrust:
SF= # #'" M U* W Stem Thrust Calculation of SF for Limitorque motor operators is as follows:
SF =
d x [(0.96815 x tan a) + p]
24 x [0.96815 - (p x tan a)]
where d = Pitch diameter p = Stem to stem nut coefficient of friction tan a= LEAD /( rr x d)
LEAD = (no. thread starts)/(no. threads per inch)
Calculation of SF For ball screw drives is as follows:
BSSF =
WD 24 x x x 0.9 1
.l ATTACHMENT ll TO JPN-94-057 TORQUE AND THRUST CALCULATION METHOD FOR <
GATE AND GLOBE MOTOR OPERATED VALVES (Page 4 of 5).
IV. MOIORIOBQUE_DERATE DUEIQAMBIENT AND MOTOR TEMPERATURES The equation to derate AC motors due to ambient or motor ternperature is:
LOS x
R,= MSTQ - MSTQ x (27900 (1.8 x RISE x TIME x 2 + (TEMP - 104)))
I where MSTO = motor rated starting torque - ft-Ibs LOSS = % torque loss /155 C RISE = motor temperature rate of rise - C/sec TIME = closing stroke time - sec TEMP = maximum ambient temperature - F, 4 DC motors are derated as follows:
NOMINAL DC MOTOR Max. Available Starting Torque (Ft-Lbs) '
STARTING TOROUE RATING at Qualified Temperature (340 F)
(Ft-Lbs) 125 Volt Rating 250 Volt Rating l 40 39 36 60 54 51 ,
80 79 68 100 70 76 I
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ATTACHMENT ll TO JPN-94-057 TORQUE AND THRUST CALCULATION METHOD FOR GATE AND GLOBE MOTOR OPERATED VALVES -l (Page 5 of 5) .
I V. CALCULATION QEMOTOR TORQUE CAPABILITY A. Actuator output motor torque capacity at rated voltage (MC100ro) is' found as follows:
MC100ro = R , X UR X E X AF where R, m = determined above UR = unit ratio.
E = pullout efficiency. If valve is closing, running efficiency may be used for sealed-in close operation. Running efficiency is not ;
l used for DC powered MOVs or for throttling valves where valve ;
may be started under load. !
AF = Application Factor ;
B. Actuator output motor torque capacity at reduced voltage (MCRVra) is derived ;
from MC10070 as follows:
MCRVra = MC1001 o X RVF where RVF = reduced voltage factor. RVF = (V/V,)2 for AC motors and V/V, for DC motors. RVF = 1 if V/V,2 0.9. i V, = reduced voltage at motor terminals -volts i
V, = rated voltage at motor terminals - volts
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i C. Actuator output torque at stall (MCSra) conditions is obtained from end of motor i curve or calculated as follows: 1 MCSto = MSTO X 1.1 X UR X SE where MSTO = motor starting torque at 100% voltage 1.1 = stall factor UR = unit ratio 1
SE = stall etficiency I
.. . . .