|
---|
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
!
123 Main Street WMe Ra%s, NewYork 10601 914 681.62(M
- > NewWrkPbwer ="~-
4# Authority l C:~
September 7, 1984 JPN-84-59 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Shift Technical Advisor Qualifications NUREG-0737 -
Item I.A.l.1
References:
- 1. PASNY Letter, J.P. Bayne to T. A. Ippolito, dated July 31, 1981 (JPN-81-57).
- 2. NYPA Letter, J.P. Bayne to D.B. Vassallo, dated January 26, 1984 (JPN-84-05).
- 3. NRC Draft Policy Statement on Engineering Expertise on Shift (Federal Register Vol. 48, No. 143, July 25, 1983).
Dear Sir:
This letter provides a description of the FitzPatrick program for the eventual phase-out of the Shift Technical Advisor (STA) position. . Reference 1 indicated that the STA position would be retained at FitzPatrick until criteria for the qualifications of operating shift personnel to fulfill the STA role were complete. In Reference 2 the NRC was informed that the Authority had initiated an Advanced Technical Training Program for Senior Reactor Operators (SROs) at FitzPatrick to provide engineering education and training that meets or exceeds the guidelines contained in Reference 3. This advanced training, for the first group of Shift Supervisors and Assistant Shift Supervisors (all holding current SRO licenses) is nearing completion.
8409100192 840907 PDR ADOCK 05000333 PDR P
a
.; ' r .,
.In additionkthe Authority has-recently received a summary of the Advisory committeelon Reactor Safeguards-(ACRS) July 12, 1984Lmeeting,lat which:NRC personnel presented to the ACRS the
. " Final Policy Statement on Engineering Expertise on Shift" as approved by the Office-~of Nuclear Reactor Regulation (NRR).
The-Authority notes'that the " final policy" is not significantlyfdifferent than the " draft policy".
The-Advanced Technical Training Program is being conducted by Memphis' State. University Center for Nuclear Studies-which is accredited =by-the Southern Association of Colleges and Schools, and is being conducted'on the FitzPatrick site. _.The. teaching staff hold faculty or. adjunct faculty rank in the Academic Department of Memphis State University. The program comprises thirteen (13) courses which are based on the STA job qualifications and responsibilities outlined in NUREG-0578.
- The thirteen courses include 540 contact hours of academic
. instruction for a total of fourty-one (41) credit hours. A
-description of courses, contact hours, and credit hours is shown^in Attachment 1.
Upon Icompletionlof training for'the first group of Shift Supervisors'and-Assistant ShiftcSupervisors in October 1984,
_ personnel will return to their regular shift duties allowing
~
another group ~to commence training in early 1985.
When"a Shift Supervisor or Assistant Shift Supervisor that has completed.the. program is on shift, that individual will also assume STA responsibilities in a " dual-role" position in a
~
manner similar to that described in the NRR. presentation to the "ACRS on July 12, 1984. Sincelinitially not enough Shift
. Supervisors or Assistant Shift Superviscrs will have completed
~_
the. program to allow complete phase-out of the STA, some operating shifts will continue to be staffed with an STA in addition to two (2) SROS (Shift Supervisor and Assistant Shift Supervisor). All shifts ~are expected to have personnel that have completed the program by the fall of 1985.
The Authority considers the criteria for the qualificatinn of Operating Shift PersonnelJto. fulfill the duties and responsibilities of the STA in a-dual-role position to be complete, and will consider those SRO's that have completed the Advanced-Technical Training Program described in Attachment 1
.as having met this criteria.
In1 addition, the Authority considers this approach to be in full compliance with the current FitzPatrick Facility Operating License and Techaical Specifications. However, in the near future, the Authority will request an amendment to the Technical Specifications which will explicitly state that qualified Shift l Supervisors and Assistant Shift Supervisors r
will-assume STA responsibilities on shift.
L._ _
c.
Jrt' JThe-Authority indicated ~in Reference l~that waivers for education, experience,.or the establishment of degree equivalency would be evaluated on a case-by-case basis for-STA candidates and that approval would be required by the Senior
.Vice President for Nuclear Generation. Since Reference 3 and
.the final policy presented to the ACRS clearly establish the
. requirements for-alternatives to a BS Degree in Engineering.for the-dual-role ~ Shift Supervisor /-STA or Assistant Shift
- Superviscr/STA,.the Authority.will not require Senior Vice President'~ Nuclear Generation 1 approval.for those non-degreed
-individuals that have successfully completed the Advanced
' Technical Training Program.
Should you or your_staffLhave-any questions concerning this matter,7please contact Mr. J. A. Gray, Jr.'ofEmy staff.
Very truly yours,
~7
. J.
- W^
. Bayne. u
'rst Executive Vice President
-ChiefLOperations Officer CC: Office of the Resident Inspector U.S. Nuclear Regulatory Commission P. 0; Box 136 Lycoming, New York . '13093 e y e4.--, -- + , , , y- - % w.4 ,, , -, --- , -.,-+w,,,v.s- -.e- - ,--,-e<*=%y e m
NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant Attachment 1 to JPN-84-59 The Advanced Technical Training Program comprises 13 courses which ' total 540 contact hours of i:,struction. Tne following synopsis. identifies the subjects covered in each course.
i SUBJECT AREA CONTACT HOURS Differential Calculus 50 l
l Integral Calculus 50 Advanced Reactor Physics 40 Materials Study Course 40 Fracture Mechanics 40 Corrosion Chemistry 40 Computer Technology 40
-Electric Generation and Transmission 40 Thermodynamics I 40 Thermodynamics II 40 40 Heat Transfer 40 Fluid Mechanics 40 Human Behavior 540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br /> *
- An additional 540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br /> of facalty contact is available to students during on-site in-classroom self-study.
l l
1 l
l 1
y [ _~ , ..
D3signadito davolop ckilloin problem
'hDT1fsrenticl{alculun:
ipolving;whichlinvolves ucocof.derivetives and functional 1
) notation,Cp'rovide;theDmathematical' basis for'further technical 1
~
Mtudies,cand: develop ~confidenceLin solving current physical' tpcoblems. applicable 4 to nuclear power. plants and the industry, lTopics include:the following:
~
- Algebra including an extension of-basic algebraic concepts-and techniqueslof; problem ~ solving: learned.in mathematics icourse(s) of Loperator license: programs Lto include the
. concepts 1and; techniques important to calculus, vector algebra, and1 complex functions.
~
1*Trigonometrysincluding^an extension of basic trigonometry-learned 1n operatorclicense: training to include-specific 3 s l trigonometric relationships _-importantito calculus-including
- the fundamental-~ identities, trigonometric formulas, and-trigonometric laws.
3
- Geometry-including the graphing and manipulation of
-specific-algebraic _ functions, an analysis of their
, properties, andltheir. relation to' physical properties of-
' materials and design.of. equipment.
4*Special Functions including functional 1 notation and manipulation, algebraic functione, algebraic series, transcendental functions,-and the relation of algebraic
-series _tofphysicalfproblems.'
-* Differentiation including the1 concept and technique of differentiation, specific formulas,. geometrical
~
interpretations, and the application-of differentiation to the solution of problems.
' *Special: Applications of differential ~calculuc to' problem solving-in physical science and application to problems-in-nuclear power plants..
c,
' Integral Calculus:- DesignedLto provide' fundamental knowledge of-the-concepts and; techniques-of calculus-and develop skill
^
1and- proficiencyfin solving ' problems necessary to effective-Q learning'in advanced technical courses. LTopics include lthe
. following:.
- Integration including introduction to the concept of integration, integration formulas,: geometric interpretations, and the application of the indefinite-Lintegral to' problem solving.-
i
- Definite IE ntegrals ~ including practice in solving definite
- integrals, geometrical. interpretation, and the application
- offdefinite_ integrals.in the solution to engineering and Dscientific problems.
- Multiple Integrals. including techniques of solving multiple integrals, and their application ~to the solution
'of problems.
_ o .
.s c
(eApplicationcJinclud'ingfan application of integral 1 calculus
^/- tofspecial-problems [in nuclecr-reactoriengineering and idesign;gthermodynamics; area; integrals on xy, PV, and.TS 1 icoordinate;: Entropyfascintegral (dQ/T); special problems:in-
. heat transfer,Kfluid-flow, and~ structural analysis.
T* Differential' Equations. including. introduction to ordinary:
- s
- Jand. partial differential 1 equations,ctheir application to R' 'physicaloproblems,Jand techniques of solution.
f
(*Special" Techniques' including an introductioncto Laplace
~ , '
Ltransforms and Fourier: analysis:and their application;to
- problem} solving.- !
JAdvanced R'eadtor Physics:: cDesigned to expandLthe student's.
knowledge of;.thes basic physics of nuclear reactors by.deta'iled -
development of concepts such as spatial-dependence of neutron cfluxes,1 neutron losses.in:the high energy: range, effects of
.heterongeneous arrangements'offreactor materials, temperature
- coefficients 1ofrreactivity,lreactorfpoisons,Leore lifetime, kinetic behavior:offneutron populations, and reactor. power ,
oscillationsv . Topics include the following:
- Neu ron'DiffusionEincluding the analytical treatment?of the diffuston; equation, physical meaning, and measurement sofcparameter:such'as the diffusion length, neutron flux' J s hapes_in'various reactor regions, leakage from-the reactor, criticality _ conditions, and suberitical multiplication.
- NeutronL Slowing-Down-including-the physics of kinetic,
' energy loss by elasticLcollisions, the moderating.
fproperties'of:various materials, the! concept of the Fermi EAge'and its-meaning initerms of: leakage. losses of1 fast
~
- . neutrons,: absorption' losses during-slowing-down'and the l' ;(absorption)'-resonance escapefprobability,'the fast effect; p vandEthe physical" basis of theLthermalization process.
<r
=* Kinetic' Behavior of Reactors including an in-depth discussion =of tne effects or prompt and delayed ~ neutrons, Emethods'for~. calculation of the-time-dependence of1the neutron fluxiafteria step change,in reactivity, the " prompt'
- jump",:.the stable' reactor ~ period,=and reactor power oscillations.. ,
p ._ ..
94 *Special' Topics including fission product poisoning, feguilibrium concentrations of xenon'and samarium'for
/T qvarious-neutron 1 flux' levels, " dead-time", fuel burn-up, 1 poison burn-out, chemical' shims and core lifetime.
!*MultiLR egion Reactor Theory including the calculation of all of the important parameters'of reflected reactors by-
- means of multi-group methods, heterogeneous
-fuel-moderator-coolant core _ arrays,' neutron density in the.
~
-vicinity of control rods'and control rod worth.
l
.-__.:________.____-___.__-__-_J____-__.__.___._________-_____-____.---___._-_.__.--______..__--___.______L_2. . _ _ _ - - -
~ - - - -
Totempardturo Effccta on' Criticality:inclu' ding 1 calculations._
fj;f_ . 'ofythe rocctivity under-various conditions,. effects of.
".4 >
changesEofDmaterial-densities on neutron leakage =and
- resonance absorption, and Doppler effects on thermal;
~
- neutron ' cross.. sections and on .the resonancef escape
< probability..
4 ' Materials' Study: Course:
An-introduction.to terminology,
- . fundamental-properties and concepts; methods of-fabrication and
- testing;'the;causes and prevention ~of failure in metals,.
. 1
-ceramics,. plastics, elastomers, lubricants, welding materials,
- and coatingsTused.in nuclear power 11ndustry'with special.
emphasis on. failure case histories of materials in nuclear -
E power-plants. Topics include the'following:
I
- Introduction >and summary of course, identification of' onjective:and othe; relation of: objectives to generic failure case' histories.
-
- Metallic?Maheria'Is' including _the mechanical behavior of metals, families ofzferrous and,non-ferrous metals, carbon R. Land-low alloy' steels forLeastings, low'and medium alloy steels,; stainless steels high-temperature high-strength-alloys'for castings,, copper, aluminum, refractory metals, s
precious metals, environmental'and service' conditions, ',
effect of= environment on materials selected for use in the
~
reactor pressure 1 vessel.and' primary systems, service epiping, codes;and. standards,'and selected examples of metal-failures.
e
- Plastics and ElastomersLincluding an introduction to the
' molecular. structure of plastics, physical properties and
- characteristics lof plastics,' applications of plastics and similar. materials, the compatability.of_ plastics with.other.
materialsf and operating = conditions, common causes of c performance failurejof plastics, codes.and standards,.and case: histories of-failures.
\
- Ceramics including an introduction to ceramic raw materials, fabrication of ceramics, physicalz properties, MT physical' structure, ceramic equil'ibrium phase, structural ,
i imperfections, codes andLstandards, and case history of
. . failures withfemphasis on fuels.
- Special: Materials. including an introduction to basic properties _and characteristics and failure modes of-1 ;
flubricants,' hydraulic fluids, protective coatings,'and q welding materials used in nuclear power plants with empgasis.upon case histories of failure.
L ,
I 4-( +
'w _. -. .
,jFrccturd M2chanica:EDDaigned to:fcmiliarize theistudsnt~with:
.. ~ _ .
f, ib thpa-f undamantaleconcepts of. fracture machanics,-froprosentativo:
^
A .cace-histories of-failures, and? develop skill-in analyzing-
- component designs?for? potential failures.and failed materials:
~
LtoidetermineLreasons;for failure. Topics include the; efollowing:.
~
- Crystalistructure! including an' introduction to
ElatticeJstructures, crystal _ defects, and: microstructure
.withespecial application to metallic. materials and ceramics.
1 1* Mechanical"Prbperties of;Metalslincluding fundamental, concepts of_ stress and strain, stress-strain diagrams, Lelasticity,fand' safety: factors with' emphasis on metals used in reactor primary; system components, and service piping.
'*ThermalIProperties of Metals ~ including conceptsrof temperature expansion heat transfer, thermal stress, and creep:with emphasis on temperature transients'in power 1 -- plants.;
- Fracture? Mechanics including a study of the fracture-mechanism and fracture mode and an analysis of common (failure; cases in components.
!* Methods of Testing including a revi'ew of materials' testing u program sucn as drop weight testing, Charpy V-notch impact-tests, Land'Charpy transition curves.
- Neutron Damage including a' study of the.effect of neutron radiation"on the properties of steels, such as nil-ductility 1 temperature,l failure case histories due-to neutron irradiation, Land design considerations in nuclear
. power plants.
1
! Corrosion - Chemis try':- Designed to' familiarize the student with
.the. basic principles underlying corrosion of' metals; the effect ofLcorrosion;Lmethods ofEprevention in' design,'use, and storage-
- of materials;;and failure case histories in generic power 6 ; plants. Topics l'nclude the following
- GeneralEAttackicorrosion as introduction.to classification of corrosion processes. Corrosion in power plants
, . operating under high pressure, stress, and temperature 7 Leonditions.: - Introduction to various specialized types of
' corrosion'significant'in causing component failures.
- Electrochemical Corrosion as based on chemical attack, but
. modified as an electrical phenomenon in which the metal ~
' atoms have an electr cal: charge as ions. Action of ions with an electric potential to cause the chemical
.transformationuof the material and galvanic theory.
A$
T h,we im__.___i .__.___..___.___m______._____.n_.__.________u_________._.__.m_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _______._.___.__.______.__.__._.__.__m__.m_ _ _ _ _ _ _ ____m_m_m
^
-0Sthinlhan-Sthhlc replacing ordinary stcols in mooting the
.' . .corronion rcuictencas required-in high-pressure
-high-temperature nuclear power plants. Stainless steels
.are more resistant to the usual corrosion processes but subject'to their own particular difficulties, including stress corrosion cracking and passivity reduction under specific unusual conditions..
- Special Corrosion Processes including crevice corrosion, stagnant corrosion, pitting,_ leaching, caustic embrittlement, chloride stres corrosion, stress fatigue, blistering, intergranular corrosion, weld decay, <
temperature sensitivity, filiform corrosion, biological attack,_etc.
- Erosion including the abrasive effect resulting from high flow rate and resulting in erosion, impingement, cavitation, fretting, etc.
- Nuclear Pressure Vessel and Tubing corrosion classified by type of equipment and frequency of occurrer. :e. General corrosion in pressurized water reactors, stress corrosion cracking in boiling water reactors, denting in tube bundles, etc. Failure case histories, methods of prevention.
Computer Technology: Designed to develop familiarity with the basics of computer science including programming languages, hardware and software systems, and applied computer logic in order to develop skill in using computer programs to solve complex engineering problems applicable to nuclear power plants. Topics include the following:
- Program Languages including a review of FORTAN IV and BASIC with emphasis placed upon input / output, program logic, arrays, sub-programs, modeling techniques, complex arithmetic, and double precision operations.
- General' Computer Technology including the theory of digital device and the. design of basic logic circuits to solve problems encountered in the nuclear industry, number systems, digital arithmetic, Boolean algebra, and reduction techniques.
- Computer Systems including analog and digital computers, large scale. computer systems, minicomputers, microcompit ers, micro- processors, and time-share systems.
- Digital Systems including advanced digital circuit design, complex digital devices and computers, input / output devices, random-access storage devices, sequential logic, and advanced integrated circuit systems.
- Problem Solving including the solution of problems applicable to tne nuclear industry by developing algorithms and utilizing " hands-on" experience in implementing programs for data assimilation and handling, instrument data interpretation, radiation transport, fluid flow, and heat transfer.
k E'lcctric Gnn0rnticn And Trennmiccion: Danigntd to davolop undarctending of the principles of electric ganaration and
- . transmission and the use of instrumentation in nuclear power plants. Topics include'the following:
- Basic Electric Generation including a review of electric fields, current flow, Coulomb's law, potential, conductors, insulators, semi-conductors, resistance, resistivity, Ohm's
-law, Kirchoff's law, circuits, motors, and generators.
- Plant Generation including a review of generator arrangement, multiphase generators, generator rating,
. voltage, efficiency, rotor and stator construction, cooling systems, excitation systems and parallel operation.
- Station Electric Circuits including familiarization with bus arrangements,. basic generator connections, control-power connections, switching equipment, circuit breakers, plant transformers, power-transforming rating, losses, efficiency, and instrument transformers.
o
- Electric Transmission including investigation of problems associated with the transmission of electrical energy, load-flow studies, and fault analysis including load variation, centralized control, power. transmission, high tension lines, and transformers.
- Instrumentation including a study of principles of controlling plant system variables, insuring reliability, and providing for the automated control of nuclear. power stations by understanding the basic operation of temperature instruments, flow transmitters, pressure measuring devices, level indicators, various electrical meters, and radiatirm monitors.
Thermodynamics I: The first course in thermodynamics covers basic concepts in energy flow and the mathematical aspects of its transformation. Thorough discussion of the exact nature of the different kinds of energy serve as a vital introduction to the general energy equation.as applied to non-flow and steady-flow' processes. Special thermodynamic properties such as enthalpy, entropy, etc. are introduced in order to
' understand the proper application of the " laws" of thermodynamics. Topicc include the following:
- Dimensions, Units, and Properties including a review of the basic units of length, area, volume, mass, and force that underlie the units and concepts of pressure, temperature, heat, and work.
'* Gas laws including the relations between pressures, volumes / and temperatures for ideal gases leading to the ;
properties of vapors such as steam.
,m
. ~
.oNon-Flow'Procica including a~ctudy of the non-flow energy
. - .cquation intur-relating heat.cnorgy, pressure energy, work energy, and enthalpy.
- Flow Processes including' flow processes which involve the general. energy equation applied to steady-flow and non-steady flow processes. The various. kinds of energy--potential energy, kinetic ~ energy, internal energy, flow energy, etc. are-examined.
- Introduction to Cycles as successive thermodynamics processes that form a closed loop or cycle that transforms heat energy into work energy. Work energy as transformed
.by'a. turbine into electrical energy. The concept of entropy as necessary in the application of the laws of thermodynamics for the understanding of the energy transformations.
- Carnot Cycle introduced as the most efficient cycle for determination or Lne available energy'that can be transformed to energy output. Unavailable energy rejected from the plant as heat to the atmosphere or to cooling water.
Thermodynamics'II: Application of the energy principles developed in the first course of thermodynamics to determine the performance of the components of equipment in the actual power plant. Topics include:
'* Water and Steam including the basic properties of water and steam as a working medium of vital importance in understanding the thermodynamic energy transformations.
- Saturation Properties defining the pressure-temperature relationship that establishes the conditions determining whether the liquid water phase, the vapor steam phase, or two-phase conditions are present. An understanding of saturation conditions is important in avoiding TMI incidents.
- Reactor Power Plant Equipment including a study of the reactor as a source of heat energy, water heaters, steam
-generators, superheaters, turbines, and condensers.
- Basic Steam Turbine thermodynamics of the simple Rankine steam cycle involving boiler generation of steam and condenser cooling.
- Feedwater/H eating involving the thermodynamics and economics of improving basic steam cycle performance by regenerative feedwater heating. Effect of steam superheating.
)
icondrnbercTh5rmodynrmica~ involved in'condrncing.stcInm
. r- through h at r@jnction to river end seawetor:and to.tho Jatmosphere tur cooling towers. Atmosphere cooling tower psychometrics are also studied.
-Heat Transfer: LA study of heat transfer.in terms of conduction,
~
convection, and radiation. Actual hea'c transfer as a combination of two or more-of these modes. Fluid flow and overall' heat transfer. Topics include the following:
- Basic Quantities ~ including a review of notation, units,
~
derinitions,. conversion, heat'and temperature effects, physical ~ properties, viccsity effects, and fluid flow effects.
- Conduction examined in terms of electrical analogy:
-heat flow,. temperature decrease as potential, thermal resistance, and thermal conductivity.
- Convection including natural laminar stream-line,-forced
-turbulent correlation by Reynolds, Nusselt, and other
' dimensionless number. parameters.
J
- Radiation including a study of the Stefan-Boltzman law, emissivity absorptivity, reflectivity, transmissivity, angle factors,-area cosine law, black and gray bodies, parallel planes, and other configurations.
- Overall Heat Transfer including thermal resistances of all kinds, thermal resistance in series and in parallel, cavities, shapes, materials, log mean temperature difference (LMTD), and heat exchangers.
- Boiling Two-Phase Heat Transfer including a study of boiling phenomena, saturation, pressure-temperature relationships, pressure to prevent boiling, burn-out, and other high-heat-flux phenomena.
- Condensation considered as boiling in a reverse direction.
Modification of pressure-temperature relatior.s due to less sensitive operation than the high pressure-temperature relationships of boiling.
- Application to heat transfer from reactor fuel pins to coolant including the properties, characteristics of fuel and fuel claddin and the effects of heat transfer.
L.
l f
. . . . _ . ._. - _ - . . _ _ _ _ - m . .
by . :1~
^~ 'St d 'u y o'f-fluid flow an a function.of
~
, 5 fluid"M$dh2nics:
-af[presuro.differenticle. _ Single:phazo flown,Jtwo pha'se1 flows
"*; hfinvolvingiliquids"and vapors. . Fluid mechanics and fluid ~
- _1
- dynamics governed:by thermodynamic energy relationshipsLand
-thermalDproperties. Secondary:effectiresulting'from-inclusion:
1 - iof heat flow .
Topics: include the following:-
- *FluidIFlow Basic Principleszincluding measurements units.
^
Properties of pressure, density,;and specific volume. _ Con-6: .tinuity_ equation. General energy. equation..
- Ideal? Fluid' FlowT without friction. ~ Basic" analysis
- jsimplification considering friction as' absent._or' minimal.
- Static dynamicfandstotal' pressure. Bernoulli. equation..
i Hydrostatic jet equation. Bernoulli head equation.
- Actual' Fluid Flow friction-effects-superimposed on'the flow of ideal fluids..~ Friction resulting in heating and the necessity 1for; examining fluid properties. Viscosity, Reynolds number, head equations with system losses. Fluid hammer.
- Fluid' Flow Measurement. based on pressure drop, volume flow 7
as-a. function of-pressure drop and pressure drop as a measure of flow-quantities. Venturis, flow nozzles, and orifice meters. Flow-measurement by other than' pressure ,
' drop.
-
- Fluid' Flow Pumps. including ideal input to pump,1 pump
-- efficiency, pump cavitation, types of' pumps, pump laws, i , pump-operatingLpoint, and pumps.in parallel.
- Fluid Flow In Turbines based on applications of the second i law or tnermodynamics. ' Single and multistage turbines.
- Nozzles.
- Mollier diagram. Convergent and pt convergent-divergent nozzles. Ejectors.
.. Human Behavior:: - A study of the basic principles of
"( psychology.necessary to: understand and/ assess personality
' traits'and how1 individuals perform on teams and~under' emergency C
E conditions. Topics include the following:
r~
- Basic Principles of- psychology in study areas such as f.
9 personality, abnormal behavior, intelligence,. learning, l, . sensation,'and perception including terminology used in i professional communication.
- rersonality' Traits. including _a study of' concepts and
-" Eprinciples in normal and abnormal behavior which will '
- develop an understanding of' patterns of' intellectual and behavioral development in-li.dividuals; allow' recognition and logical assessment of deviations from' normal behavior, e
. V
+
fnnurotic end p:ychotic recctionct.dsvelop cn understanding-E c.- - of organic, ganstic, and environm:ntal influences on
' personality; and provide a method of identifying specific personality traits and-predicting behavior under specific
' circumstances.
- Social Traits as a study of the behavior of individuals in group settings including cooperation,' leadership, inter-group and intra-group relations which will develop
. skill in recognizing' leadership and identifying individuals who cannot. work cooperatively with teams.
- Applied Psychology in the industrial setting with emphasis-on methods of selecting personnel, aptitudes, classification and evaluation of personnel, understanding and interpretation of employee attitudes, morale and motivation, understanding influence of work conditions and environments, and an introduction to methods of testing and screening-of job applicants.
- Applications including an analysis of the impact of personal and social traits upon individcal and group performance in selected accidents which fill develop skill in assessing potential personal failures under conditions of stress.
Academic Credit is awarded as follows to students who successfully complete courses of the Advanced Technical Training Program.
~
Course Number Course Title Semester Credit Hour
-MATH 1321 Analytical Geometry & Calculus 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> MATH 2321 Analytical Geometry & Calculus 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> TECH 3413 Materials Structure and Properties 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> CHEM 3010 Corrosion Laemistry 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> PHYS 3703 Stress Mechanics 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
! PHYS 4510 Thermodynamics 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> CHEM 3031 Chemical Thermodynamics 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> PHYS 3702 Nuclear Heat Mechanics 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> PHYS 3701 Physics of Fluids 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ELEC 4202 Electrical Power Systems 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> PHYS 4221 Advanced Reactor Physics 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> TECH 3262 Computer Applications in Nuclear Power 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> PSYC 3599 Special Topics in Applied' Psychology 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 41 Credit Hours
--in'cddition to ths 41 credit'houra'for ths.13 courses licted
~
. Ibtvs, two;(2) project coureca of 3 credit hours each are to be completed.- For these projects each student will select a specific component or system of a nuclear power-plant and perform an analysis. The projects planned for-this component l of the program' are intended ~to -develop competence and experience in.the analysis of systems, the assessment of operating experience, and in accident response. The-student will learn to apply existing methodology for accident analysis to the particular case chosen for the project and document the results of his study in a report which he must. defend in peer level as well as academic reviews.
- Technical Report-Writing Instruction will be given to students enrolled in the project courses on technical report writing. This instruction will provide the student '
with the basic information needed to professionally prepare technical reports.
- Analysis Techniques Techniques will be provided to students enrolled in the project courses. These techniques will include methodology of analyzing systems, components, and technical reports.
- Projects Two projects are planned for this component of' the program, each of which will serve as a separate 3 credit hour course.
- Reports A written report thoroughly documenting the study performed in each project'and its results is required.
Successful completion of the course is largely-based upon the report.
- Faculty.The projects are administered by members of the University faculty. Participation of plant management in project reviews will be solicited.
c