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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
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_ _ _ - _ _ _ - _ _ - _ _ _ _ - _ -
James A.Mt:Pstrick Nuctsar Power Plant
. P.O. Box 41 Lycoming, New York 13093 316 342-3640 8D NewYorkPower
(# Authority Clam"L"!r""
April 15, 1991
- JAFP 91-0228 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 ttn
- Mr. Charles W. Hohl, Director - Division of Reactor Projects
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT -
DOCKET NO. 50-333 UPDATE OF THE STATUS OF ACTIVITIES FOR THE EMERGENCY SERVICE WATER SYSTEM
References:
- a. NRC letter, C.W. Hehl to W. Fernandez dated October 9, 1990 regarding August 21, 1990 enforcement conference.
- b. NYPA letter, J.C. Brons to NRC dated January 16, 1990 (JPN-90-011) regarding proposed change to the Technical Specifications regarding crescent area unit coolers improvement (JPTS-89-032) .
- c. NRC letter, D.E. LaBarge to J. C. Bronc dated April 11, 1990 regarding issuance of Technical Specification Amendment 156.
\ttachments: 1. Update of the Status of Previous HRC Commitments presented at the August 21, 1990 Enforcement Conference
- 2. ESW System Testing Program
- 3. As-built Crescent Area Unit Cooler Control Configuration Description
] ear Mr. Hehl:
[n Referenco (a) the NRC staff requested that the Authority prepare snd submit a report summarizing the current status of known
- ommitments associated with the FitzPatrick Emergency Service Water lESW) System and the crescent area coolers. The staff also asked
. hat the Authority address the ESW system testing program, any ESW system related Technical Specification changes that the Authority light propose, and a revised response to NRC Generic Letter 89-13,
' Service Water System Problems Af fecting Safety-Related Equipment."
04290296 910415 R ADOCK 05000333 PDR St O l. Ih
\ ,.
U.'S. Nuclear Regulatory Commission April 15, 1991 Attn: Document Control Desk JAFP 91-0228
SUBJECT:
JAMES A FITZPATRICK NUCLEAR Page POWER PLANT -
DOCKET NO. 50-333 UPDATE OF THE STATUS OF ACTIVITIES FOR THE EMERGENCY SERVICE WATER SYSTEM NRC Generic Letter 89-13 The Authority will submit an updated response to NRC generic letter 89-13 not later than April 30, 1991.
ESW - Crescent Area Cooler Commitments Authority commitments associated with either the ESW system or crescent area coolers are summarized in Attachment 1. This-version reflects and minorthe current status of ESW/ crescent area cooler commitments editorial improvements. A previous version was distributed at the August 21, 1990 enforcement conference.
ESW Test Procram DescriDtion The Authority's ESW test program at FitzPatrick is summarized in Attachment 2. It briefly describes each of the surveillance tests, the test frequency and the components tested.
Technical Snecification Imorovements During the August 21, 1990 ESW enforcement conference, the Authority identified the limitations of the " shut off head" .ESW pump surveili.ance test currently required by the FitzPatrick Technical Specifications. The Authority will propose a Technical Specification change to revise the test requirements to be consistent with the appropriate portions of ASME Section XI-and the FitzPatrick inservice inspection and test program. The surveillance tests and minimum acceptance criteria will be similar to those approved by the NRC for other licensees. The test currently The under consideration will require relief from Section XI.
Authority will prepare and submit technical specification changes no later than September 1, 1991.
Update on Crescent Area Unit Cooler Modifications To improve the reliability of the crescent area coolers, the Authority recently completed modifications that will reduce the potential for silt accumulation in the coolers. Instead of
- U..S. Nuclear Regulatory Commiesion April 15, 1991 l Attn: Document Control Desk JAFP 91-0226 SUILTECT: JAMES A FITZPATRICK NUCLEAR Page POWER PLANT -
DCCKET NO. 50-333 OPDATE OF THE STATUS OF ACTIVITIES V)R THE EMERGENCY SERVICE WATER LYSTEM throttling cooling water flow to the coolers, continuous cooling water flow is being supplied to the coils of 8 of the 10 unit coolers. Control circuits were modified to actuate the cooler fans as a function of area temperature. Technical Specification changes associated with these improvements were submitted by the Authority (ReMerence b) and subsequently approved by the NRC (Reference c).
The carrent configuration of the crescent area unit cooler control syster is not consistent with the description included in the authortty's application. A design change, prepared and approved after kmendment 156 to the Technical Specifications had been issued by the NRC, reduced the number of coolers affected by the modification from ten to eight. However, the actual Technical Specifications pages issued by the NRC are unaffected by these alterations; the FitzPatrick Technical Specifications are correct and accurate. The conclusions in the Authority's safety evaluation are still valid.
The NRC Project Manager for FitzPatrick, after being notified of this change, asked that the Authority submit a description of the modifications as they were installed. Attachment 3 is a brief description of the crescent area cooler control system as it exists today.
Any questions regarding the matters discussed above should be addressed to Mr. Christopher Ponzi of my staff at (315) 349-6564.
Very truly yours, f j (V/
)ILLIAM FERN DEZ II
/
WP:CJP:bnrk Attachments' CC: U.S. Nuclear Regulatory Commission Document Control Desk Mail Station Pl-137 Washington, D.C. 20555 R. Liseno NRC Resident Inspector RMS (WPO)
V. Walz J. Gray (WPO) TS File DCC R. Ram (WPO) IST File
A. LER 88-009-01 COMMITMENTS STATUS
- 1. Install permanent instrumentation to monitor crescent cooler thermal COMPLETE performance.
- 2. Siweekly crescent cooler testing until modifications are completed. ON-GOING - Biweekly testing will continue until the current cooler performance reassessment is completed.
l 3. Modify crescent unit cooler fan and water controls to allow full water COMPLETE l flow, cycle the fan and install additional therr.:a1 performance instrumentation. The modification was to be installed prior to start-up from 1990 Refuel Outag':. The Completion date was delayed until September 30, 1990 (JPN-90-11). The modification has beer. completed.
B. RESPONSE TO VIOLATION 88 INOPERABLE CRESCENT COOLER &
COMMITMENTS ,
STATUS
- 1. Revise ST-19A to better measure cooler performance bi-weekly. COMPLETE
- 2. Clean and inspect coolers. COMPLETE
- 3. Reanalyze crescent cooler heat' loads to' demonstrate acc. , tab:e cc0 it with r,0MPLETE service water temperature up to 82*F.
- 4. Modify piping to reduce accumulation of suspended solids. INCOMPLETE -
Modification: will be determined by the effects that full flow through the crescent coolers and chlorine injection have on silt and corrosion deposits.
~Page l
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ATTACHMENT 1 . - ,
STATUS OF PREVIOUS NRC COMNI?4ENTS B. RESPONSE TO VIOLATION 88 INOPERABLE CRESCENT COOLERS (couth ui d) l CONNITMENTS STATUS
- 5. Install larger mesh strainers. COMPLETE '
- 6. Replace missing section of flanged pipe to UC-22J. COMPLETE
- 7. Revise piping arrangement to UC-22D. COMPLETE
'8. . Initiate performance testing of other service water-cooled safety-related COMPLETE heat exchangers.
- 9. Maintain accelerated test frequency-for crescent area unit coolers until DN-G0ING - Biweekly performance trend improves. testing will continue until the current cooler '
performance reassessment is. completed.
- 10. Review all[ Technical Specification surveillance requirements and ensure COMPLETE they are: contained.in STs and are performed on schedule.
- 11. Establish System Engineering Group. COMPLETE
- 12. . Reorganize the WPO Engineering Staff so that engineering personnel are COMPLETE assigned exclusively to the Authority's nuclear plants.- -This corporate engineering organization reportsidirectly to the Executive Vice President-for Nuclear Generation.,
- 13. " Develop' Medification: Control Manual and . Design Change Manual. PARTIALLY COMPLETE.
The Modification Control Manual is complete. The Design Control Manual has been implemented at the corporate office and is scheduled to be implemented at the Site by 7/1/91.
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!?___'_______.____ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _
B. RESPONS_E TO VIOJ.ATION 88 INOPERABLE CRESCENT COOLERS (continued)
STATUS COMMITMENTS PARTIALLY COMPLETE (WACP
- 14. Develop a formal root cause analysis program. 10.1.27) - The procedure for root cause analysis methodology has been implemented. An integrated causal action program has been .;
defined. The imple-menting procedure is '
being developed for initiation this summer.
C. RESPONSE TO VIOLATION 88 HIGH SERVICE WATER TEMPERATURE STATUS COMMITMENTS Revise FSAR to address 82*F lake temperatures. Awaiting incorporation INCOMPLETE
- 1. Safety Evaluation is-into revisior. complete. FSAR Change Request has been submitted and will be incorporated into the 1991 FSAR update. !
COMPLETE
- 2. Train engineering personnel on 10 CFR 50.59 safety evaluation preparation and importance. l
- 3. Fonnalize the method for promptly evaluating deviations from the FSAR. COMPLETE (NGP-38)
COMPLETE
- 4. Train. plant management personnel on the reportability requirements of 10 CFR 50.72.
Page l
ATTACHMENT 1 STATUS OF PREVIOUS NRC C0dMITMENTS L
D. ENFORCEMENT CONFERENCE COMMITMENTS STATUS
.In addition to the commitments contained in Section (B) above, the Authority committed to the following:
-1. Trend test data to establish testing and maintenance frequency to prevent CONTINUING flow restrictions. Testing and maintenance is currently being reassessed. Trending of teste data will continue until reassessment is complete.
- 2. Evaluate the feasibility and necessity of testing other safety-related COMPLETE
! coolers.
- 3. Develop administrative procedures describing the responsibilities and COMPLETE establishing the various channels to be utilized by the Systems Engineering Group..
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t I
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Y
, ATTACHMENT 2 ,
E8W SYSTEM TESTING PROGRAM
- 1. The safety-related heat exchangers listed below 'are or may be supplied cooling water by the.ESW. system.
emergency diesel _ generator jacket cooling wateri heat '
exchangers (93WE-1A, -1B,'-1C, -1D) electric bay unit coolers (67UC-16A, -B) cable. tunnel /switchgear room'coolersE(67E-11, -14) control room and relay room air handling units (70AHU-3A,
-3B, -12A and -12B) crescent area unit coolers (66UC-22A, -B, -C, -D, -E,: -F,
-G, -H, -J, -K)
- 2. The following is 5 summary of surveillance testing procedures!
for the ESW system valves, pumps,-logic-circuitry and' heat exchangers..
ST-80, ESW Motor ODerated Valves' Operability Test *
Description:
- ESW MOVs are cycled by their-control switches to verify proper remote manual operation.
Components Tested: 15MOV-101 46MOV-101A' 15MOV-102 46MOV-101B 15MOV-103 46MOV-102A-15MOV-175A 46MOV-102B 15MOV-175B i
Frequency: Monthly.
( ST-8D, E8W Pumo Flow Rate Test (IST)* l
Description:
_The shutof f ' head of each pump is' measured-l separately-to. demonstrate;that the ESW' pumps.
satisfy the Technical. Specification flow.rato requirements. The 'ESW MOVs are also stroke time tested during this--test for IST.
, Components Tested: 46P-2A,B ESW pumps l 46MOV-101A,B- . ESW system injection valves 46MOV-102A,B' ESW system ^ test. valves Frequency: Quarterly ~
Page -l'-
ATTACKMENT 2
- 2. Continued ST-8E, ESW Locic System Functional Test and Simulated )
Automatic Actuation Test *
Description:
Demonstrates the ability of Reactor Building Closed Loop Cooling (RBCLC) pump discharge header pressure- switches and associated Lockout Matrix relays to cause Emergency Service Water Pumps to start and specific MOVs in the RBCLC and ESW systems to reposition to an ESW injection to RBCLC lineup.
Components Tested:
15PS-122A pressure switches 15PS-122B 15PS-122C 15PS-122D 46P-2A,B ESW pumps 15MOV-175A,B ESW return to service water MOVs 46MOV-101A,B ESW system injection valves 46MOV-102A,B ESW system test valves Frequency: Quarterly ST-8N, ESW Pump Inservice Test (IST)*
Description:
Each ESW pump is run in a standard lineup to permit collection of required IST data. Pump discharge check valves and Emergency Diesel Generator (EDG) return line check valves are verified to open.
Components Tested:
46P-2A,B ESW pumps 46ESW-1A,8 ESW pump discharge check valves 46ESW-6A,B EDG return line check valves Frequency: Quarterly ST-8P, ESW Return Check Valves Reverse Flow Test *
Description:
Verify EDG return line check valves close.
Components Tested: 46ESW-6A,B EDG return line check valves Frequency: Once per cycle Page ,
, ATTACHMENT 2
- 2. Continued ST-80, Testina of the Emeraency Service Water System (IST)
Description:
The ESW flow rates to raw water heat exchangers is measured to confirm that flow rates - to the units meets the design- basis. The test also demonstrates that various ESW check valves open.
Components Tested:; .
67UC-16A,B electric bay. unit coolers 67E-ll',14 cable' tunnel /switchgear_ room coolers 70RWC-2A,B control room chiller condensers 70AHU-19A,B. control, room chiller' room coolers
.66UC-22A to K- crescent-area _ unit coolers 93WE-A,B,C,D EDG jacket water coolers-46ESW-1A,B ESW-pump discharge check. valves 46ESW-6A,B EDG return'line~ check valves 46ESW-7A,B ESW _to . control rm. _ equip. check valves 46ESW-9A,B ESW to-reactor building check-. valves-46ESW-13A,B ESW'to crescent cooler check valves s Frequency: Quarterly BT-8R, Emeraency Service Water Check Valve Test (IST)*
Description:
The proper operationL of interfacing ' : ESW and normal service water check valves is verified by flushing ESW through-the check valves _to verify they open and then manipulating the appropriate
- a
, valves to reverse flow through-the check valve and measuring-leakage through.-a drain connection upstream of the check valve to verify it . has ,
closed. Safety-related r SWS. check valves are ~
verified to-close by measuring leakage.through a drain connection upstream of.the-. valve. ,
Components Tested: Check Valves- !
46ESW-19A,B: 46(70)SWS-101 46ESW 20A,B _ '4 6 (70) SWS-102 46ESW-21A,B- 46SWS-60A,B' 46ESW-22A,B 46SWS-67A,B 46SWS-68 46SWS-69 Frequency:. Monthly i
Page -
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l ATTACHMENT 2 I
l
- 2. Continued BT-19A, Crescent Area Unit Cooler Performance Test
Description:
Thermal performance of the crescent area unit coolers is measured. Normal service water is the cooling medium for this test.
Components Tested: 66UC-22A,B,C,D,E,F,G,H,J,K crescent area unit coolers Frequency: Quarterly (presently the unit coolers are tested biweekly)
BT-J9B, Electric Bay Unit Cooler Performance Test *
Description:
The thermal performance of the electric bay unit coolers (67UC-16A,B) is determined. Normal service water is the cooling medium for this test.
Components Tested: 67UC-16A,B electric bay unit coolers Frequency: Semi-annual BT-19C, Crescent Area Unit Cooler Performance Test with ESW Flow
Description:
This test determines the heat removal capability of the crescent area unit coolers. Emergency Service Water is the' cooling medium for this test.
Components Tested: 66UC-22A,B,C,D,E,F,G,H,J,K crescent ~ area unit coolers Frequency: Semi-annual ST-19D, Cable Tunnel Ventilation Cooler Performance Test *
Description:
This test determines the heat removal capability of the cable tunnel /switchgear room coolers.
Normal service water is the cooling medium . for this test.
Components Tested: 67E-11,14' cable _ tunnel /switchgear room coolers Frequency: Semi-annual Page - _ _ _ _
l ATTACHMENT 2
- 2. Continued ST-19F, Crescent Area Unit Cooler Performance Verification Test *
Description:
This test verifies crescent area . unit cooler thermal performance using hand held monitoring-test equipment instead of the permanently installed test equipment.
Coinponents Tested: 660C-22A,B,C,D,E,F,G,H,J,K crescent area:
unit coolers.
Frequency: Semi-annual S7-19G. Electric Bay Unit Cooler PerformaDoe Test with ESW Flow *
Description:
This test determines the heat removal capability of the electric bay unit coolers. Emergency service water is the cooling medium for this test.
Components Tested: 670C-16A,B electric bay unit coolers Frequency: Semi-annual-ST-19H. Cable Tunnel Ventilation Cooler > Performance Test with EH
Description:
This test determines the heat removal capability
-of the cable tunnel ventilation coolers.
Emergency service water is the cooling medium for this-test.
Components Tested: 67E-11, 14 cable tunnel /switchgear room coolers Frequency: Semi-annual other -
Heat Exchancers that are not Currently Performance Tested The following safety-related heat' exchangers are capable of being supplied by the ESW system and are not presently subject-to thermal performance testing. Other methods are used to assure their proper performance as described below.
A. Emergency Diesel Generator Jacket Water Coolers, 1A,1B,1C and 1D. 93WE-Page _. _
ATTACHMENT 2 These units are periodically disassembled, inspected and eddy current tested in lieu of performance testing. The cooling medium for these units is ESW. Operability of these heat exchangers is demonstrated by monthly operation and surveillance testing of the Emergency Diesel Generators. ST-8Q verifies the design basis flow rates to these units are met.
B. Control Room and Relay Room Air Handling Units,.70AHU-3A,
-3B, -12A and -12B.
These units provide cooling for the Control Room and Relay Room areas. The cooling medium for the units is a closed loop glycol system with a service water and Emergency Service Water backup which must be manually valved in._ The development of performance tests for these units is currently under consideration. It is undesirable to drain the glycol from the AHUs and flush lake water through them.
Presently, ST-8Q is performed to measure ESW flow to nonsafety-related control room ventilation equipment which is supplied by the same piping as the Control Room and Relay Room AHUs. Since the nonsafety-related units require a higher design basis flow rate than the safety-related units, this test verifies that adequate ESW flow to 70AHU-3A, 3B, 12A and 12B would be obtained if they were m.bnylly valved in.
Page ~6-
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E' ' ATTACHMENT 3 l-o New York Power l Authority 1 James A. FitzPatrick Nuclear Power Plant' As-built Crescent Area-Unit Cooler ControllConflaurationi Introduction To improve the reliability of the crescent area -. unit coolers, the j Authority- recently= completed modifications ' that; will reduce. the- o potential for silt accumulation. Instead .of throttling cooling- water c flow to the coolers,. continuous cooling water flowLis supplied to thei =
coils. Control-circuits:were modified to actuate-the-cooler--fans as a function of. area . temperature.. T e c h n i c a l-- S p e c i f i c a t i o n -; c h a n g e s :
associated with these' improvements were. submitted by1the; Authority, 1 (Reference b)'andssubsequently approved bydthe NRC as: Amendment (156f ,
(Reference c). =
a q
A design-change, prepared-and^ approved1aftereAmendmentil56LtoLthe-Technical Specifications .had been, is'suedlbyt the ' NRC, reduced T the i q number 1of coolers affected :-bylthe modification- fromi en t J tot eight. s This change was made due: co 'potentialL technicallproblemsf associated with excessive ' fan ? cycling - of thel unit - coolers.J . . To prevent? this problem-only eight of the unit cool'ars were< modified.'-The" remaining two coolers-(one in-_each crescent = area), provide cooling;as;they?did
~
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originally; The service water flow rate isLstillithrottled by the TCV -
I c but at a higher flow rate because the other eight unit: coolers provide q little or noJ. cooling ~during;normalEoperating;conditionsqwhen their-fans are off. The actual TechnicalLSpecifications pagesiissued!by the? '
NRC as part of Amendment 156 are unaffected by these alterations. 'The- j FitzPatrick Technical specifications?are correctiand' accurate.1 !The i conclusions.in the Authority's safety evaluation Jare still valid " j
-While the amended' Technical; Specifications .'pages'iss'ued by.the NRC are ,
unaffacted,by these alterations,'the7 current,configurationidoes;not' 4 agree withLtheodescription included in theLAuthority'sjapplication.-
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The NRC Project Manager /for FitzPatrick,xafter?being notified ofLthi's) ]
~ change,: , asked that 'the'; Authority . submit! af description /'of: lthe' i
modifications as4they were: installed.4~ :Thecparagraphatbelow describe ?
the . crescent ' area! cooler ?controliconfiguration. - OtherJunitVcooler, <
modifications, notLrelated to"thefTechnicalRSpecifications,c areinote
-described.-
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- Pre-modification- Crescent 2 Area cooler Des'li2n
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- The.. Reactor Building Crescent ' Areas i are; cooledLby Lten: air-to-water-
, heat exchangers'.' , These' ten ' coolers: are dividedrinto two trains. Five coolers' are installed in'each crescent area.- Air ris drawn' across the A cooler'sJcoils by a motor driven fan.
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.'- ATTACHMeny 3 Under non-accident conditions, cooling water is supplied by the Service Water System (SWS). In the event of an accident, the Emergency Service Water (ESW) System supplies cooling water when the SWS may not be available.
Pneumatically-operated Temperature Control Valves (TCVs) installed in the supply line to each unit cooler originally throttled the flow of
- cooling water. Ten Temperature Indicating and Control Switches (TICS, i
one per cooler) were used to sense area temperature and regulate air pressure to the TCVs as a function of area temperature. Increased area temperature sensed by the TICS would in turn change the air pressure to the TCVs. The TCVs would open, thereby increasing flow to the cooler and lowering area temperature. On a loss of pneumatic supply, the TCVs move to their open position.
Prior to installation of this modification, the fans ran continuously during normal operating conditions. Ten control switches in the main control room could be used to turn each fan on or off.
These coolers were sized to reduce the temperature of the air in the crescent area in the event of a design basis loss-of-coolant accident (LOCA). Since heat loads in the crescent during normal plant operations are significantly lower than those t.een during a LOCA, the TCVs were essentially closed allowing little or no flow through the
, coolers. With little or no flow through these lines, any suspended solids (such as silt) accumulated in the coolers. This condition was further aggravated by the fact that the coolers are situated at the lowest points in the SW/ESW piping.
1990 Refuelino Modifications During the 1990 refueling outage, eight of the ten coolers were modified. Two coolers were not modified and flow through those coolers are still controlled using TICS and TCVs in the supply piping.
l For the eight modified coolers, TCVs were removed from the cooler l
supply piping. This will allow approximately 24 gpm to flow continuously through the coils of these eight coolers.
The fan control circuitry for these eight coolers was modified so that Temperature Control Switches (TCS) turn the fans on as a function of l area temperature. Fans motors must be turned off (de-energized) l manually to minimize excessive cycling of the fans and eliminate the l need for frequent replncement of the TCS. The fan motors can also be l started manually from the control room.
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ATTACHMENT-3 l
l The TCS setpoints are staggered so that the fans are energized over a range of temperatures. As the temperature in each crescent increases, additional fans will automatically . start. Within each crescent, one cooler fan will start when the temperature reaches 85 degrees F; a second fan in each crescent will start when the
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temperature reaches 90 degrees F; one more at 95 degrees;-and, the last at 100 degrees F. When the-air temperature exceeds 100 degrees, the four fans-in that area will have automatically started.
One cooler in each crescent continues to function using the old TICS /TCV control system. During normal conditions, this one cooler will remove the heat generated by equipment in its area. The SWS ' flow to this cooler will still be throttled by a TCV but the flow rate'in its coils will be increased since the other four coolers will provide I little or no cooling.
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