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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1851999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request ML20212F8341999-09-22022 September 1999 Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 ML20210U2621999-08-12012 August 1999 Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds ML20216D9421999-07-28028 July 1999 Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal ML20210A7001999-07-16016 July 1999 Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20209D5511999-07-0606 July 1999 Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept ML20196G2981999-06-18018 June 1999 Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant ML20196L1451999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) ML20207D9191999-05-27027 May 1999 Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl ML20207A6751999-05-17017 May 1999 Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls ML20206N0721999-05-11011 May 1999 Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20206C8551999-04-27027 April 1999 Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205P1991999-04-0909 April 1999 Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARJPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JPN-99-011, Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing1999-04-0505 April 1999 Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing ML20205G4111999-03-31031 March 1999 Forwards Rev 7 to JAFNPP EP App J & Rev 6,pages 7 & 8 to EAP-5.3 05000333/LER-1999-001, Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments1999-03-31031 March 1999 Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments JPN-99-008, Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl1999-03-31031 March 1999 Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl JPN-99-010, Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP1999-03-31031 March 1999 Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP JAFP-99-0114, Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl1999-03-29029 March 1999 Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl JAFP-99-0112, Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested1999-03-29029 March 1999 Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested JAFP-99-0097, Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years1999-03-17017 March 1999 Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years ML20204B6241999-03-17017 March 1999 Forwards Plant Referenced Simulation Facility Four Year Performance Testing Rept, Per 10CFR55.45(b)ii 05000333/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept1999-03-16016 March 1999 Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept ML20204C7371999-03-15015 March 1999 Forwards Revised EP Coversheets for Sections to Vol 1 & Rev 26,Vol 3 to EPIP SAP-10, Meteorological Monitoring Sys Surveillance JAFP-99-0085, Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable1999-03-0808 March 1999 Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable ML20207J3201999-03-0505 March 1999 Forwards Form NRC-369,requesting That Restriction for Corrective Lenses Be Placed on Current License SOP-10089-3, for Ks Allen.Encl Withheld Per 10CFR2.790(a)(6).Without Encl JAFP-99-0073, Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments1999-02-26026 February 1999 Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments JAFP-99-0071, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-02-25025 February 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0068, Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting..1999-02-22022 February 1999 Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting.. JAFP-99-0019, Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS1999-01-25025 January 1999 Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS JAFP-99-0012, Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys1999-01-18018 January 1999 Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys 1999-09-08
[Table view] Category: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
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123 Main Street White Plains, New York 10601 914 681.6240
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September 11, 1985 JPN-85-66 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 Request for Submittal of a Revised Procedures Generation Package
References:
- 1. NYPA Letter JPN-83-60 dated June 30, 1983 from J. P. Bayne to D. B. Vassallo regarding Require-ments For Emergency Response Capability
- 2. NRC Letter dated June 10, 1985 from D. B. Vassallo to J. C. Brons regarding Interim Safety Evaluations On The Procedures Generation Package The NRC Generic Letter No. 82-33 required the Authority to submit a Procedures Generation Package (PGP) in support of the development and implementation of upgraded Emergency Operating Procedures (EOPs). The PGP consisted of four parts: Plant-Specific Technical Guidelines, a Writers Guide, a validation program description and a description of the training program for upgraded EOPs. The Authority submitted a PGP for our FitzPatrick plant via reference No. 1. The EOPs themselves were implemented December 29, 1984 in accordance with our commitment to the NRC.
Via Reference No. 2, the NRC requested that the Authority submit a revised Procedures Generation Package to address each of the items included in your Interim Safety Evaluation. The four attachments to this letter constitute our response to your request.
Attachment No. 1 is a point-by-point response to each comment in the Interim Safety Evaluation. Attachment No. 2 is the revised FitzPatrick Emergency Procedure Guidelines (EPGs) (Rev. 3),
(Revision 3 of the BWROG Generic EPGs formed the basis for the Fitzpatrick EOPs.) Attachment No. 3 is the Writers Guide (Administrative Procedure 2.2). Attachment No. 4 is a summary of significant differences between the FitzPatrick EPGs (Rev. 3) and the BWROG EPGs (Rev. 3).
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nuring the two years between our submittal of the PGP and our receipt of your comments, significant changes were made to the
!: Writers Guide to resolve difficulties in implementing the EOPs.
Also during this time, the Authority has participated in the BWROG effort to prepare a new revision of the generic CPGs. ,
Additional changes to the FitzPatrick EPGs and Writer's Guide will be incorporated as specified in Attachment 1. Further changes will also be incorporated as required by the final issuance of the generic EPGs by the BWR Owner's Group. (This next revision is scheduled for subrcittal to the NRC in late 1985. ) Due to the nature of the Emergency Operating Procedures and the training required to support significant changes in them, major revisions to the EPGs, Writer's Guide and EOPs will not be undertaken until final issuance and approval of-the generic EPGs.
If you have any further questions regarding FitzPatrick's PGP,
! please contact Mr. J. A. Gray, Jr. of my staff.
Very truly yours M
ohn . Brons i ienior Vice President f luclear Generation
! cc: Office of the Resident Inspector l U.S. Nuclear Regulatory Commission j P.O. Box 136 i Lycoming, NY 13093 f
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. NEW YORK POWER AUTHORITY James A. FitzPatrick Nuclear Power Plant ATTACHMENT 1 TO JPN-85-66 Response to NRC Letter Dated June 10, 1985,
" Interim Safety Evaluation on the Procedures Generation Package" A. Technical Guidelines for Emergency Operating Procedures General
- 1. Comment: The P-STG should identify safety significant deviations from the EPG's along with a justification for each deviation.
Response: Attachment 4 summarizes the significant deviations of FitzPatrick's P-STG (Attachment 2), as compared to the Boiling Water Reactors Owners Group (BWROG)
EPG's, (Revision 3 dated December 8, 1982) which were approved by the NRC staff in November 1983.
- 2. Comment: Attachment 1, AP 2.2, Item 7.1.4 is not clear on how " problems" are resolved; "The checklist is returned to the water (SIC) for resolutions of problems".
Response: AP 2.2 has been revised (Attachment 3) to require that the reviewer sign the technical guidelines cover sheet thus signifying agreement. The paragraph implies that the writer resolves the problems with the reviewer. If agreement cannot be reached, plant procedures require plant management and/or PORC resolution.
- 3. Comment: Provide a description of the process for using the EPGs and background information_to identify' control room operator tasks and information and control needs.
This process can be described in either.the revised PGP or in the Detailed Control Room Design Review (DCRDR) program plan with appropriate cross referencing.
Response: The Authority transmitted a supplement to the FitzPatrick DCRDR Program Plan via letter dated August 31, 1983 (Reference 7). This supplement included details about control room operator tasks and information and control needs.
The methodology used for the CRDR task analysis relies heavily on the " Graphic Display Development" project of the BWROG Display and Procedures Integration Committee. This l
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' project, which was funded by EPRI and the USDOE, under the direction of.the BWROG, produced, among other products, a functional analysis of the BWROG Generic Emergency Procedure Guidelines. The information requirements (both
- implict and explict), decisions and actions required by the
- operator were identified for each step of the generic EPGs. In accordance with the direction from the USNRC Human Factors Engineering Branch, the Authority has worked
- to maintain the independence of the process for determination of the information and control requirements from the specifics of the FitzPatrick control room. For this reason, the human factors contractor retained by NYPA for the DCRDR project task analysis was instructed to use this generic functional analysis of the BWROG/EPGs as the j starting point in the determination of the information and control needs for the task analysis. The contractor will use the information and control needs of the generic analysis and-then identify the information and control needs'from the plant specific EPGs for those steps which are at variance with the generic guidelines. These needs will be determinded without regard to the design of the Fit 2 Patrick control room by examining the generic analysis and its plant specific adaptation, the Fitzpatrick EPGs.
The " process" is thus to simply examine actual steps of the EPGs and determine the information and control needs for those steps which vary from the generic analysis, for which these needs have already been determined.- Note that while
- the generic analysis does not identify specific control requirements, it does identify required actions. The human factors consultant will use his BWR experience to determine the required controls to carry out these actions.
A summary description, similar to the one above, will be included-in the FitzPatrick DCRDR Summary Report.
i specific i 1. Comment: Page 14, RC/P-1 Graph - Caution #18 reference
- should-be Caution 98 (ref. generic guideline RC-5).
Response: This correction has been made. (See Attachment 2.)
- 2. Comment
- Page 16, RC/P Part of last bullet is~ relevant to the first two bullets and is thus improperly placed ....
Response: This correction has been made. (See Attachment 2.)
l 3. Comment: Page 17, RC/Q Why is the CRD system the only l system identified for boron injection as the alternative to ,
1 SLC1 l l l 1
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r-Response: CRD system modifications to allow a relatively easy and quick alternate boron injection path are currently under consideration. Some of the other systems listed, although potentially available, do not lend themselves to easy use and therefore were not included.
- 4. Comment: Page 22, DW/T Discuss the bases for the drywell spray flow rate restrictions of less than 1800 gpm and the derivation of the drywell spray initiation pressure limit.
Response: The drywell spray flow rate has been increased
'to 10,000 gpm (see Attachment 2) as a result of further refinements in the BWR Owner's Group calculation procedures. The drywell spray initiation pressure limit is based on the BWR Owner's Group calculation procedure 9.0, (Revision 3A, dated March 1, 1984 in Appendix C of the BWROG Generic EPG's).
- 5. Comment: Page 23, PC/P The word " pressure" was left out between " chamber" and " exceeds".
Response: The word " pressure" was added. (see Attachment ,
2.)
- 6. Comment: Page 25, PC/P Where is plot associated with limit? (As per guideline?)
Response: The drywell spray initiation pressure limit plot was erroneously omitted and has been added. (See Attachment 2.)
- 7. Comment: Page 26, SP/L - Do you have SPMS?
Response: FitzPatrick does not have a separate SPMS.
Several methods are available for suppression pool water make-up.
- 8. Comment: Page 28, SP/L-3.2 - As Mark 1 containment, other parts of step should be included as per guideline.
Response: The generic guideline includes other sections which are applicable for Mark l containments with internal suppression-chamber-to-drywell vacuum breakers.
FitzPatrick does not have internal breakers: PitzPatrick is equipped with external vacuum breakers.
- 9. Comment: Page 30, Operator Actions - Actions in the EPGs isolate only HVAC. Actions in the P-STGS imply more than HVAC is isolated.
Response: The FitzPatrick EPGs have been revised (Attachment 2) to clearly specify that Reactor Building (secondary containment) ventilation be isolated and SBGT (Standby Gas Treatment System) be initiated. These actions L______________________________________________
are required by the generic guideline to terminate any radioactive release and to assure negative pressure within secondary containment.
- 10. Comment: Page 32, Table 1 - Under secondary containment parameter / location, why has refuel floor been left out?
Response: The refuel floor temperature and instrument 66-TI-106 (66-FN-13A and B inlet temperature) are the same. The wording has been clarified. (See Attachment 2.)
- 11. Comment: Page 37, Cl Why is the fire system not included in alternate injection systems?
Response: The alternate systems listed are "hard-piped" and can be easily lined up for injection. The fire system would require a lot of jumpers and " jury-rigs" to use it for alternate injection.
- 12. Comment: Pa guidelfnes, ge it 44, C5-6.3 would appear....that Based the on the generic minimum RPV flooding pressure should be higher than the minimum SRV re-opening pressure. Please clarify.
Response: This has been corrected. (See Attachment 2.)
The minimum RPV flooding pressure is 84 psig; minimum SRV re-opening pressure is 50 psig.
B. FitzPatrick Writer's Guide for Emergency Operating Procedures General As a result of difficulties encountered when preparing the Emergency Operation Procedures, the Writer's Guide was significantly revised prior to EOP implementation. The revised Writer's Guide (AP 2.2) is included as Attachment 3.
The Writer's Guide includes a new EOP layout which has a logic format with entry conditions and' operator actions on right-hand pages, and corresponding override statements and figures on left-hand pages. This new format was reviewed by a human factors consultant who reacted favorably.
Specific Comments
- 1. Comment: Information should be presented in procedures so that interruptions in its flow are minimal. To achieve this, each procedure should be written so that an action step, a warning (caution), or a note should be completed on the page where it began. This guidance should be included in the writer's guide.
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Response: The Writer's Guide (Attachment 3) requirement for conciseness and precision in instructions naturally achieves these results. More specific guidance will be provided in a future revision of the Writer's Guide.
- 2. Comment:' Placekeeping aids can assist the operators in keeping track of their position within a procedure. They are of particular importance when performing concurrent steps or procedures and in situations when the user's attention may be diverted. Thus, the writer's guide should be revised to specify some type of placekeeping aid.
Response: The Authority agrees with this comment and several placekeeping aids are presently being considered.
A mechanism for placekeeping will be incorporated in the EOP revisions which result from the completion of the BWROG's work.
- 3. _ Comment: It is important that an operator be able to quickly access the relevant EOPs or portions of the EOPs.
The writer's guide should address the accessibility of the EOPs and their various parts and sections. See NUREG-0899, Subsections 6.1.3, for additional guidance.
Response: The EOPs, (as with all operating procedures),
are readily accessible to the on-shift operators. Each EOP is clearly. identified with a cover sheet as specified in Appendix A, Section 2.1 (Attachment 3). In addition, the EOPs located in the control room have been tabbed to allow easy access to key parts of the procedure. The Writer's Guide, will be revised to include guidance on the use of tabs.
- 4. Comment: The writer's guide should include guidance for units of measure for use in instructional steps, and they should be the same as the rules for the use of units of measure in tables and figures discussed in Subsection 4.9.1, on page 22 of 53.
Response: Guidance for numerical values is given in Subsection 5.5 of Appendix A. (See Attachment 3.)
- 5. comment: Abbreviations, acronyms and symbols are discussed in Section 5.6 on page 29 of 53. To ensure that these items are recognizable by the operators, a list of acceptable abbreviations, acronyms and symbols should be included in the writer's guide. See NUREG-0899, Subsection 5.6.2, for additional guidance.
Response: The plant-specific EPG lists, in Table 1, common abbreviations used in the EOPs. Additionally, NUREG-0899, Subsection 5.6.2 suggests that the abbreviations used are familiar to operators so that there is no need to consult a glossary. No further list is necessary.
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- 6. Comment: To minimize confusion, delay, and errors in execution of the EOPs steps, the following concerns should be addressed in the writer's guide: (1) EOPs should be structured so that they can be executed by the minimum shift staffing and minimum control room staffing required by the facility's Technical Specifications, (2) instructions for structuring the EOPs should be consistent with roles and responsibilities of the operators, (3) actions steps should be structured so as to minimize the movement of personnel around the control room while carrying out procedural steps, and (4) action steps should be structured to avoid unintentional duplication of tasks.
See NUREG-0899, Section 5.8, for additional guidance.
Response: Emergency Operating Procedures were written to implement the requirements of the EPGs. The generic EPGs were generated with appropriate consideration of control room operator's performance capabilities and requirements.
The EPGs, and consequently the EOPs, do not address time sequences since this would imply specific events rather than symptoms. The roles and responsibilities of the operating shift are defined in AP 1.1 " Composition and Responsibilities of Plant Organization", and other required procedures. All operating procedures take this into account. Therefore, no further instructions are necessary.
- 7. Comment: Action steps need to be written for a variety of situations. The writer's guide should address the formatting of the following types of action steps: (1) verification steps which are used to determine whether the objective of a task or sequence of actions has been achieved, (2) steps which are repeatedly performed, (3) steps for which a number of alternative actions are equally acceptable, and (4) steps performed concurrently with other steps. See NUREG-0899, Section 5.7, for additional guidance.
Response: The revised Writer's Guide (Attachment 3) specifically addresses the formatting of various types of action steps. Additionally, the procedure format was specifically designed to accommodate instructional steps which may become applicable at any time while executing the procedure (i.e. " override" steps).
- 8. Comment: Section 4.2 on pages 18 and 19 of 53 contains a good discussion on the use of logic terms. Logic statements Could be Confusing if the statements are not written in a consistent format. Therefore, this section should be expanded to specify the format and include an example of how these logic statements should be written.
See NUREG-0899, Subsection 5.6.10 and Appendix B, for additional guidance.
Response: This section has been expanded and now includes examples. (See Attachment 3.) -
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- 9. Comment: Subsection 3.2.b on page 16 of 53 discusses the content of the entry conditions, which are to be placed in the Symptoms section of the EOP. However, the format of the Symptoms section also needs to be specified. The format used in Figure 2 on page 15 of 53 is in paragraph form, which could be confusing to the operators if there are a large number of entry conditions and symptoms. This subsection should be expanded to specify that a list of type of format should be used to present the symptoms and entry conditions in the EOPs.
Response: This section has been substantially changed and addresses these concerns. (See Attachment 3.)
- 10. Comment: Use of equipment and control label information in the EOPs should be applied consistently. The writer's guide should identify the specific information to be included and the format for presenting the equipment and control label information.
Response: Section 4.7 of The Writer's Guide (Attachment 3) provides guidance on component identification.
- 11. Comment: Section 2.4 on page 14 of 53 states that each page of the procedure will be identified by the procedure title designator and number, the revision number and the page number. The example of Page Format, on page 15 of 53, includes the title of the EOP. If the licensee intends to include the title on each page of the EOP, the writer's guide should be changed to so specify.
Response: A comma between title and designator was erroneously omitted. The title will appear on each page.
- 12. Comment: The left and right hand margins are discussed in Section 6.2 on page 30 of 53. This section should be expanded to include a specification for the top and bottom margins.
Response: Figure 2 of The Writer's Guide (Attachment 3) provides the page format and consequently controls the top and bottom margins. The applicable section will be expanded to include discussion on top and bottom margins in the next revision of AP 2.2.
- 13. Comment: The methods of reproduction are described in Section 7 on page 33 of 53. Since copies of the EOPs should be complete (contain all of the information from the original) and legible, the criteria regarding completeness and legibility of the reproduced copies should also be addressed in the writer's guide. See tiUREG-0099, Subsections 6.2.2, for additional guidance.
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Response: This section will be expanded in the next revision of AP 2.2 to more thoroughly address the criteria for completeness and legibility.
- 14. Comment: The following inconsistencies or errors in the writer's guide should be corrected:
- a. The line spacing in Figure 2 on page 15 of 53 does not correspond with the text in Section 6.3 on page 30 of
- 53. The spacing in Figure 2 appears to be single line spacing with double line spacing between headings and text. Section 6.3 calls for 3 line spaces between headings and text and 1 1/2 line spaces for the text.
The example should be made consistent with the instructions in the writer's guide.
- b. Section 3.2 on page 16 of 53 states that the procedures will have four section headings: TITLE, SYMPTOMS, AUTOMATIC ACTIONS (not applicable in symptom-oriented procedures) and OPERATOR ACTIONS.
(i) However, the example in Figure 2 on page 15 has TITLE, SYMPTOMS and IMMEDIATE ACTION as the three section headings. The example should be corrected.
(ii) In Subsection 4.9.3, on page 22 of 53, it is stated that "Section numbering for attachments should be in accordance with subsection 3.3".
This indicates that ATTACHMENTS are meant to be a major section, and should be listed in Section 3.2.
- c. Subsection 4.9.3, on page 22 of 53, states that attachment page numbering is to meet the requirements of Subsection 2.5. This should be corrected to say it '
is to meet the requirements of Subsection 2.4.
- d. The page numbers in the Table of Contents for the writer's guide do not match the page numbers in the writer's guide. The Table of Contents should be corrected.
Response: The most recent revision of Ap 2.2 (Attachment
- 3) has an accurate Table of Contents. The remaining comments do not apply to the current revision of Ap 2.2.
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C. Emergency Operating Procedure Verification / Validation
- 1. Comment: The verification program as outlined.in Section 7.3 on page 5 of 53 and in Appendices B and C of the
" Procedures for E0Ps" contains most of the necessary elements that are required to meet the objectives of NUREG-0899. However, in order to ensure the technical'and human engineering adequacy of the EOPs, the verification and validation programs should specify that the teams performing the verification and validation include both subject matter experts and procedure writers in addition to the reactor operators who are already included in the program. See NUREG-0899, subsection 3.3.5, for additional guidance.
Response: The E0Ps were prepared by consultants who are heavily involved with the BWROG's Generic EPG work (subject experts) and who also utilized a human factors engineer in the procedure development. In addition, the consultants were significantly involved with the validation process.
The Writer's Guide will be revised to more clearly specify that future verification and validation events will include a subject matter " expert" and a procedure writer (s). The subject matter " expert" will be knowledgeable in Appendix B (technical basis) of the EPGs and the procedure writer (s) will be familiar with the requirements of the Writer's Guide.
- 2. Comment: The use of scenarios in the validation process are described in Subsection 7.4.1.1 on page 6 of 53. This subsection should be expanded to specify that the scenarios include multiple (sequential and simultaneous) failures.
Response: This subsection will be expanded in the next revision. The simulator exercises performed in 1984 for EOP validation and operator training did include multiple failure scenarios.
- 3. Comment: The discussion of simulator sessions in Subsection 7.4.3.2 indicates that a normal crew of operators will be used. The PGP should indicate that the EOPs will be exercised during plant walk-throughs and simulator events with the minimum control room staff size required by the facility's Technical Specifications.
Response: Section 5.8.1 of NUREG-0899 recommends that E0Ps not require mare than minimum shift staffing as defined by Technical Specifications. AP 2.2 (Attachment 3), reflects this in Section 7.4.3.2 and in AP 2.2, (Appendix D, part B2) which requires a validation assessment to the following question, "Could the procedure action steps be performed by the operating shift?" PitzPatrick's EOPs strongly parallel the EPGs and delineate required actiona, but not time, L----____--___---_--_--_----____----_--_-.-_____--- - - - - _ _ _ _ _ - - - - - - - - - - - - - - - - . - _ - - - - - - - _ _ _ _ _ _ _ - - - _ _ _ _ - -
m since this would be event-oriented. Therefore, it would be inappropriate to mention minimum control room staff size since the remainder of the shift is readily available.
- 4. Comment: To assure verification / validation of all the EOPs, the program description should include an indication that the full complement of EOPs will be exercised.
Response: The validation and verification steps of the Writer's Guide must be accomplished before each EOP is approved. Therefore, it would be redundant to add this wording.
- 5. Comment: There are discrepancies between the writer's guide and Appendix B, "EOP Verification Checklist
- that should be corrected. These are as follows:
- a. The writer's guide includes instructions on procedure organization and step numbering in Section 3.0, component identification in Section 4.0, and vocabulary, abbreviations and typing instructions in Sections 5.0 and 6.0. These items are not covered in Appendix B.
- b. Conversely, Appendix B checklist, Item 7 deals with listing or specifying the recipient of a communication in the EOP which is not mentioned in the writer's guide,.and checklist item 9 asks whether provisions are made for verifying automatic actions associated with the emergency were actually observed, whereas the writer's guide, and checklist item 9 asks whether provisions are made for verifying automatic actions associated with the emergency were actually observed, whereas the writer's guide stated the automatic actions are not applicable in symptom-oriented procedures.
Response: Appendix B was significantly changed in the revised AP 2.2 (Attachment 3). Most of these comments have been resolved in this revision.
D. Emergency Operating Procedure Training Program General Since the EOPs have already been implemented, inclusion of additional wording in the PGP is unnecessary. Our reply to each question will respond to the comment and describe what was done in 1984 to support EOP implementation.
Specific
- 1. Comment: The program description should clearly state the training objectives, e.g., t'tainees should understand the philosophy behind the approach to the EOPs, and how these objectives will be accomplished by the training program.
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Response: Lesson plans were prepared and used to support the classroom training phase of EOP training. Each lesson plan stated the training objectives.
- 2. comment: Since the licensee must use a generic simulator for training, discuss the methods to be used to train the operators in areas where the simulator is not like the control room or does not react like the plant, and in parts of the EOPs that cannot be run on the simulator.
Response: Operators were trained on the EOPs, including tabletop discussions, prior to simulator training. At the simulator, additional tabletop discussions were conducted on the differences between the simulator and FitzPatrick.
l A staff instructor and a representative of the consultant responsible for EOP preparation were also present at the t simulator to assist in training and to discuss differences between FitzPatrick and the simulator.
! 3. comment: Indication that operators will be trained as a i team to use the EOPs and that each operator is trained in the role that they would be expected to take in case of an actual emergency.
Response: Training was conducted using normal shift complements. Licensed operators rotated positions at the simulator to receive training outside their normal roles.
This was in addition to their normal role training.
l 4. comment: Indication that a wide variety of scenarios will be used to fully exercise the EOPs on the simulator (within the constraints of the simulator).
1 Response: This was done at the simulator, (in addition to multiple failure scenarios), to exercise and train operators on all EOPs.
l 5. comment: Indication that all the EOPs will be exercised in some fashion by all the operators.
Response: The simulator training included exercise on all EOPs with all operating shifts.
- 6. Comment: The description of the training program should i include a statement of commitment that all operators will '
l be trained on the revised EOPs prior to their I implementation.
l Response: The extent of operator training on revised EOPs l necessary before implementation depends on the extent of the revisions. Prior to implementing the original EOPs, l revisions were made after simulator training to correct problems identified at the simulator. Operators were ,
required to read these changes before standing watch.
Future revisions will be assessed on a case-by-case basis. l l
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- 7. Comment: The description of the training program should state that the operator's knowledge and performance on the EOPs will be evaluated and that appropriate follow-up training will be conducted in deficient areas.
Response: This evaluate and follow-up feature is a routine part of the FitzPatrick training program mandated by other regulatory requirements. The original simulator training included this evaluation and follow-up training. Future training programs will also include this feature.
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References
- 1. NYPA letter, J. P. Bayne to D. B. Vassallo, dated October 24, 1983 (JPN-83-90) regarding Supplement No. 1 to NUREG-0737, item I.D.1, Control Room Design Review.
- 2. NRC letter, D. B. Vassallo to J. C. Brons, dated June 10, 1985 regarding Interim Safety Evaluations on the Procedures Generation Package.
- 3. NRC Generic Letter No. 82-33, Supplement No. I to NUREG-0737, dated December 17, 1982.
- 4. NYPA letter, J. P. Bayne to D. B. Vassallo, dated June 30, 1983 regarding Supplement 1 to NUREG-0737, Requirements for
, Emergency Response Capability. Includes: Administrative Procedure 2.2 (Procedure for Emergency Operating Procedures; and a summary of the EOP training program.
- 5. NRC Generic Letter No. 83-05, dated February 8, 1983, safety Evaluation of " Emergency Procedure Guidelines, Revision 2" NEDO-24934, June 1982.
- 6. NRC letter dated November 23, 1983, D. M. Crutchfield to T.
Dente, regarding Safety Evaluation of " Emergency Procedure Guidelines", Revision 3.
- 7. NYPA letter dated August 31, 1984, J. P. Bayne to D. B.
Vassallo , (JPN-84-57) regarding Supplement No. 1 to NUREG-0737, Item I.D.1, Detailed Control Room Design Review (DCRDR).
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