|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1851999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request ML20212F8341999-09-22022 September 1999 Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 ML20210U2621999-08-12012 August 1999 Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds ML20216D9421999-07-28028 July 1999 Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal ML20210A7001999-07-16016 July 1999 Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20209D5511999-07-0606 July 1999 Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept ML20196G2981999-06-18018 June 1999 Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant ML20196L1451999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) ML20207D9191999-05-27027 May 1999 Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl ML20207A6751999-05-17017 May 1999 Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls ML20206N0721999-05-11011 May 1999 Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20206C8551999-04-27027 April 1999 Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205P1991999-04-0909 April 1999 Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARJPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999 Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1 JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999 Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999 Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999 Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999 Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999 Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld 05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999 Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999 Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999 Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999 Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999 JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999 Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999 Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999 Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1) JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999 Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999 Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl ML20210C9031999-06-30030 June 1999 Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999 Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999 Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999 Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999 Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1) JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999 Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999 Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999 Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4 ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999 Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999 Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999 Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1) ML20205M8941999-04-0707 April 1999 Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager JPN-99-011, Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing1999-04-0505 April 1999 Forwards Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will Delegate Responsibilities to Another Staff Member,In Writing ML20205G4111999-03-31031 March 1999 Forwards Rev 7 to JAFNPP EP App J & Rev 6,pages 7 & 8 to EAP-5.3 05000333/LER-1999-001, Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments1999-03-31031 March 1999 Forwards LER 99-001-01 Re Incorrect EDG line-up During Fire Placing Plant in Outside Design Basis.Suppl Contains Results of Completed Root Cause Evaluations & Subsequent Corrective Actions Taken.Rept Contains No Commitments JPN-99-008, Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl1999-03-31031 March 1999 Forwards Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433, Rev 1.Synopsis of LAR for Conversion to Its,Pending Lars, List of Subsections,Scope of Changes & Commitments,Encl JPN-99-010, Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP1999-03-31031 March 1999 Transmits Revised Exemption Request from Some of Requirements of 10CFR50,App R.Exemption Would Permit Use of CS for Rc Makeup to Achieve Safe Shutdown in Fire Area XI at JAFNPP JAFP-99-0114, Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl1999-03-29029 March 1999 Requests That License OP-11037,for Bs Brooks,Be re-issued Without Restriction for Corrective Lenses.Nrc Form 369,encl. Without Encl JAFP-99-0112, Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested1999-03-29029 March 1999 Informs of Util Determination That Listed Individuals No Longer Need to Maintain Operating License for Ja FitzPatrick Nuclear Plant.Termination of Listed Licenses,Requested JAFP-99-0097, Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years1999-03-17017 March 1999 Forwards JAFNPP Referenced Simulation Facility Four Year Performance Testing Rept, Containing Description of Performance Testing Completed During Past Four Years & Description of Testing Scheduled During Next Four Years ML20204B6241999-03-17017 March 1999 Forwards Plant Referenced Simulation Facility Four Year Performance Testing Rept, Per 10CFR55.45(b)ii 05000333/LER-1999-003, Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept1999-03-16016 March 1999 Forwards LER 99-003-00,per 10CFR50.73(a)(2)(i)(B).One New Commitment Is Contained in Rept ML20204C7371999-03-15015 March 1999 Forwards Revised EP Coversheets for Sections to Vol 1 & Rev 26,Vol 3 to EPIP SAP-10, Meteorological Monitoring Sys Surveillance JAFP-99-0085, Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable1999-03-0808 March 1999 Submits in-vessel Visual Insp Summary Rept for RFO 13 for Ja FitzPatrick Nuclear Power Plant.All Relevant Indications Recorded During Insp Were Satisfactorily Dispositioned IAW Util Internal C/A Tracking Sys & Were Found Acceptable ML20207J3201999-03-0505 March 1999 Forwards Form NRC-369,requesting That Restriction for Corrective Lenses Be Placed on Current License SOP-10089-3, for Ks Allen.Encl Withheld Per 10CFR2.790(a)(6).Without Encl JAFP-99-0073, Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments1999-02-26026 February 1999 Submits Annual Rept on SRV Challenges & Failures,Per Plant TS 6.9.A.2.b.No Challenges to SRVs from Automatic Control Circuits or from RCS Pressure Transients,Occurred.Ltr Contains No New Commitments JAFP-99-0071, Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-02-25025 February 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for Period of 980701-1231. Format Used for Effluent Data Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4 JAFP-99-0068, Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting..1999-02-22022 February 1999 Forwards Form NRC-5 Equivalent Records of All Individuals Monitored at JAFNPP from 980101-1231 on Electronic Media, Per 10CFR20.2206(b) & App a of NRC Reg Guide 8.7, Instruction for Recording & Reporting.. JAFP-99-0019, Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS1999-01-25025 January 1999 Informs of Licensee Intent to Upgrade ERDS at Ja FitzPatrick in Preparation for Year 2000 (Y2K) Readiness,Per GL 98-01. Encl Contains Brief Summary of Proposed Changes to ERDS JAFP-99-0012, Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys1999-01-18018 January 1999 Documents Util Position Re Methodology for LPRM Calibr During Reactor Operation Using Traversing In-core Probe Sys 1999-09-08
[Table view] |
Text
e.
% Nuclear Eower Ptrit 268 Lats Rotd 6 p o go 41 Lycoming New York 13093 l
315 342 3840
- > NewYo.rkPower uien,eu. coio,n3
& Authonty s.1. e eevi,v. omc.,
1 September 9, 1997 JAFP-97-0325 United States Nuclear Regulatory Commission
! Attn: Document Control Desk Mail Station P1 137 l
Washington, D.C. 20555 i
SUBJECT:
James A. FitzPatrick Nuclear Power Plant l Docket No. 50 333 I Response to Request for Additional Information Regarding the Proposed Technical Specification change to Section 6.5.1.6
References:
- 1. USNRC letter, Karen R. Cotton to James Knubel, dated June 25, 1997
Dear Sir:
This 16tter transmits the Authority's response to a recent request for additional information pertaining to a proposed Technical Specification Amendment to delete the requirements for the Plant Operating Review Committee (PORC) to review the fire protection program and implementing procedures.
Attachment 1 provides a response to the requests for information regarding the screening process used for the determination that a safety evaluation or an environmental impact evaluation is required, how procedure changes are documented, reviewed, approved, and implemented, and the administrative burden that would be eliminated from the PORC.
Attachment 2 is a table listing the fire protection program changes that were reviewed by PORC for the previous 2 years.
There are no commitments contained in this response if you have any questions, please contact Mr. Robert Steigerwald at (315) 349 6209.
Very truly yours;
%& Michael J. Colomb 7)
MJC:RS:las cc: next page
,,,, ,m ;.n n, Ill.l!Wi.lOl.l]I.ll!I.llM. ll.ll!!I.ll
@709 Ho olqq
R:gional Administrator U. S. Nuct;;r R:gul: tory Commission 475 Allendale Road King of Prussia, PA 19406 i
Office of the Resident inspector U. S. Nucles. Regulatory Commission P.O. Box 136 Lycoming, NY 13093 ,
i
- Ms. K. Cotton, Acting Project Manager Project Directorate 11
. Division of Reactor Projects l/Il U. S. Nuclear Reguicory Comrr.ission Mail Stop 14 B2 Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203 6399
.7 - . - -
j Attxhm:nt 1
!* Response to RAI Regarding Proposed Technical Snecification Change to Smetion 6.5.1.8 l
Request 1:
j Provide a ':::-!pt . of the screening process for the fire protection program and l ,
procedures and of the criteria used to determine whether or not a safety evaluation j and/or an environmental impact evaluation is needed.
Response
' AP-02.04, Revision 8 " Control of Procedures", requires Technical Specification j related procedures to have nuclear safety and environmental impact screens j completed, por MCW4, " Nuclear Safety and Environmental impact Screens and
- Nuclear Safety Evaluations", during the revision process.
f .
l Technical Specifications section 6.8.(A).3 establishes procedures which implement j the Fire Protection Program as Technical Specification related procedures, j Administrative procedure AP-14.01, " Fire Protection Program", section 8.1.4 j invokes the MCM 4 process for Fire Protection Plan revisions. The MCM 4 process j generically described below applies to procedures which implemant the Fine L Protection Program.
i i The requirements of 10CFR50.59 are implemented via a Modification Control
! Manual (MCM) procedure, MCM-4, revision 4, " Nuclear Safety and Environmental l Impact Screens and Nuclear Safety Evaluations." MCM-4 is used in conjunction j with other procedures to control a variety of activities such as Modificatic.1s and
- Procedure Changes (Operating, Maintenance, Surveillance, Administrative, etc.), to achieve compliance with 10CFR50.59.
MCM-4 uses a two step process. The first step is a screen to determine if a i Nuclear Safety Evaluation (NSE) is required. The second step, if required, is to perform the detailed safety evaluation, j Nuclear Safety and Environmental Impact Screens (NSEIS) are used to determine if a proposed activity requires a 10CFR50.59L Nuclear Safety Evaluation, a Technical l
Specification Amendment, or an Environmental impact review. NSEIS consist of I five questions which are broken into multiple parts. The answers are prepared by a j qualified individual following the requirements and guidance in the MCM-4.
The first three questions of the NSEIS pertain to the Safety Analysis Report (SAR).
4 The FSAR sections that were reviewed in answering the NSEl questions are required i to be listed. The first part of each of these three questions determines if the activity being performed is: (1) described in the SAR, or (2) affects SSCs described j in the SAR, or (3) involves a test. Written guidance is provided to the preparer to 4 determine what needs to be considered when deciding if the information is i
described in the SAR. A "YES" answer to any of these three questions requires i that the remaining parts of the question be answered. The remaining parts
} determine if the activity being performed is consistent with the requirements of the
! SAR. Written guidance is provided to the preparer in answering these questions.
The questions are posed such that a "YES" answer requires en NSE to be Page 1 of 4
i Attachm:nt 1 i- Response to RAI Regarding Proposed Technical Snecification Chance to Section 8.5.1.8 performed. "NO" answers do not require an NSE but do require written justification 4- as to why the activity la consistent with the requirements of the SAR.
2
- The fourth question pertains to the facility Technical Specification. The first part of
- this question determines if tbg activity involves items described in the facility l Technical Specification.- The lechnical Specification sections that were reviewed in I
! answering the questions are required to be listed. A "YES" answer to this part of
- the' question requires that the remaining parts be answc. red. The remaining parts of l I the question determine if the activity is consistent with the Technical Specification.
I "YES" answers require that a Technical Specification Amendment be processed in l accordance with Licensing procedures. "NO" answers require written justification
- as to why the activity is consistent with the requirements of the Technical 1 Specification, i
) The fifth question determines if the task has radiological or a non radiological environmental impact. A "YES" answer requires notification of the Radiological
! Environmental Services Manager for the preparation of an Environmental impact
- review, i
i
- NSEIS are completed and approved by qualified safety reviewers per MCM-4 l
revision 4. The approver checks for completeness, procedure compliance, and sound logic of the written justifications and conclusions.
l j' Request 2:
j For fire protection program and procedure changes that do not require a safety
- evaluadon or environmental impact evaluation, describe how the changes are documented, reviewed, approved, and implemented. Identify whether or not the l
- process is procedurainted and identify the organizational responsibilities for following
- the process, whether proceduralized or not.
Response
AP-02.04, revision 8, " Control of Procedures," govern the process for controlling the properation, review, approval, issuance, and revision of procedures. AP 02.01, j " Procedure Writing Manual," describes the standard format for site procedures and supplementa AP 02.04.
i i
1 Page 2 of 4
. o Attachment 1 Response to RAI Regarding Proposed Technical Snacification change to Baction 8.5.1.8 The Site Executive Officer assigns a Responsible Procedure Owner (RPO) for each procedure. The RPO is the management individual having overall responsibility for the adequacy and accwacy of the procedure controlling the specified activities. The RPO is responsible for preparation of procedures and assigns procedure writers knowledgeable in the area being addressed by the procedure and in the requirements of AP-02.01, revision 6. The RPO is also responsible for ensuring that new procedures, revisions, and withdrawals are properly reviewed (including cross-disciplinary), approved r.nd implemented in accordance with AP-02.04, " Control of Procedures."
Procedure chsngn may be accomplished as temporary or permanent changes.
Temporary changes are limited to non-intent changes. The review requirements for both permanent and temporary changes are the same. The review requirements require two Qualified Technical Reviewers (OTMs) knowledgeable in the affected functional areas and additional cross disciplinary reviewers as identified by the QTRs, AP-02.04, or the Responsible Procedure Owner (RPO).- Approval of permanent changea are made by the responsible procedure owner, and since Fire Protection implementing procedures are Technical Specification related, the RPO's General Manager or the Site Executive Officer,in accordance with AP 02.04 The JAF Fire Protection Program'(FPP) is described in administrative procedure AP-14.01, " Fire Protection, Program", along with the change controls for the various documents included in the FPP. The FPP is divided in to " bases" documents and
" supporting" documents. The FPP " bases" documents include the Fire Protection Plan, FSAR sections containing fire protection related information, fire protection related portions of AP-01.04, " Technical Specification Related Requirements, Lists, and Tables," and AP 14.01; changes to these " bases" documents require a full Nuclear Safety Evaluation per MCM-4, which require PORC review, The FPP
" supporting" documents include the Fire Hazards Analysis and the 10CFR50, Appendix R Reassessment which require a 10CFR50.59 Safety impact Screen per MCM-4 for all changes. AP-14.01 classifies FPP working procedures as Technical Specification Related (TSR) thereby ensuring each revision will receive a 10CFR50.59 Safety impact Screen. FPP Pre-Fire Plans are controlled per AP 14.01 which establishes the Fire Protection Supervisor as the RPO and require two qualified technical reviewers per AP-02.04. Per AP-14.01, one of the OTR's shall be an Operations department SRO for changes to Pre-Fire Plans containing safety related equipment. In addition, AP-02.04 requires that fire protection related procedures require an additional screening process to determine if the proposed changes could effect 10 CFR 50.48, Appendix R requirements or Branch Technical Position (BTP) 9-5.1, Appendix A guidelines.
The James A. FitzPatrick plant has procedurally controlled programs in place which define the fire protection program and the process for controlling changes to the fire protection program and procedures. The strength of these processes is based upon the multiple level of qualified reviews fu new and revised procedures. An additional PORC review does not provide any additional safety benefit and is an administrative burden to PORC.
Page 3 of 4
Att:-:hm:nt 1 Response to RAI Regarding Proposed
. Technical Snecification Change to Section 6.5.1.6 i-i Request 3:
I For the previous 2 years, provide an itemised summary of the fire protection i program changee' that were reviewed by the PORC. In addition, for each item, indcate 11 whether er riot it would have required a safety and/or environmental i impact evaluation and therefore, PORC review, if the proposed TS amendment had !
been in place durhg that period, enj 1 if the PORC approved the change as proposed or required a change in the proposal which provided a safety benefit, in
! . the context of the information provided, be more specific regarding the j administrative burden that would be eliminated from the PORC.
Response
l Attachment 2 provides a table which lists the fire protection program changes from July 1995 through June 1997. The table also shows whether a safety and/or onvironmental impact evaluation would have been required if the amendment was in place,if the PORC approved the change as proposed, or required a change in the l
j proposal which provided a safety benefit. As the table in attachment 2 indicates i
there were a large number of changes presented to the PORC. The majority of these changes were administrative in nature and did not require a safety evaluation l~ and/or environmental impact evaluation. Also, the PORC review did not make any l
- changes to the proposals that added any safety benefit. The determination that PORC did not add any safety benefit was based on a review of the PORC minutes -
l e
and did not include a review of pre-PORC member review comments. It is important l
to note that regardless if the proposed TS amendment was in place or not the same process would have been used to determine if a safety evaluation and/or environmental impact evaluation was required, as described above. The PORC I- would be alleviated from the administrative burden of reviewing all changes to the fire protection program by allowing the current process, described above, to control
[
' the program changes. Any changes to the licensing bases would require a PORC I review of the change via the safety evaluation and/or environmental impact i evaluation. 4 l
k l
1 I
i Page 4 of 4 f
i Attachment 2 Response to RAI Regarding Proposed Technical Soscification Chance to Section 6.5.1.6
! PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY 3 PROCEDURE NO. NO. TITLE NSE REQUIRED (YlN) BENEFIT (Y/N) .
AP-01.04 10 Tech Spec Related Requirements, Lists, and Y N Tables * (JAF-SE-95-096, R1) i (JAF-SE-94-108, RO) !
AP-14.01 O Fire Protection Program
AP-14.02 4 Combustibles and Flammable Material N N Control' ,
AP-14.02 5 Combustibles and Flammable Material N N Control' .
ARP-FPP-A 2 CO2 System Hose Reel Actuated Alarms Red N N Light
- ARP-FPP-B 3 Water Spray Valve 'Open Alarms Red Light
- N N ARP-FPP-C 4 CO2 System High Temperature Alarms N N l ARP-FPP-D 3 Water Spray Systems High Temperature N N t Alarms Yellow Light
- ARP-FPP-E 3 Water Spray Systein Supervisory Alarm Green N N Light
- ARP-FPP-F 3 CO2 System Supervisory Alarms Green Light' N N ,[
Page 1 of 17 i
Attachment 2 Response to 3Al Regarding Proposed Technical Specification Chanoe .o Section 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ARP-FPP-G 3 fonizatio1 Detectors - Smoke Detected Yellow N N Light
- ARP-FPP-H 2 fonization Detectors - Supervisory Alarm N N Green Light *
, ARP-FPP-l 2 Fire Door Alarm - Open Red Light' N N l
l ARP-FPP-J 2 Multiplexer Trouble Green Light
- N N l ARP-FPP-K 2 CO210-Ton Tank Pressure High/Lov or Level N N Low Green Light' ARP-FPP-L 2 CO2 3-Ton Tank Pressure High/ Low or Level N N-Low Green Light
- ARP-FPP-N 2 Diesel Fire Pump Trouble Green Light
- N N ARP-FPP-O 2 Electric Fire Pump - Loss of Power Gre ,n N N Light' ARP-FPP-Q 3 Foam System Not Reset Alarm Green Light
- N N ARP-FPP-R 3 Wetpipe Sprinkler System Actuation Alarms N N Red Light
- ARP-FPP-S 2 Header Valve Position Alarms Green Light
ARP-FPP-T 4 CO2 System Valve Open Alarms Red Light' N N Page 2 of 17
Attachment 2 Response to RAI Regarding Proposed Technical Specification Chanoe to Section 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY :
PROCEDURE NO. NG. TITLE NSE REQUIRED (Y/N) BENEFIT (YlN)
ARP-FPP-V 3 HPCI Foam System Flow Alarm Red Light" N N ARP-FPP-W 2 A(B) Standby Gas Treatment Train - High N N Temperature Yellow Light
- ARP-FPP-Y 1 EPIC Halon System Detection System Ye!!ow N N Light" 1 ARP-FPP-Z 1 EPIC Halon System Activation Red Light' N N FO-AD-OO3-41802 O Nuclear Plant Services Quality Assurance N N ?
Records for FitzPatrick* t FO-OP-032-41802 2 Setup and Operating Procedure for RDS-1000 N N :
Unit #9 at James A. FitzPatrick Nuclear
- FPP-1.0 11 Fire Protection and Prevention Program
- N N FPP-1.15 0 Out Buildings Emergency Action and Fire N N i Protection Plan
FPP-1.16 0 Fire Panel Alarm Response-Non-Power Block' N N )
l FPP-2.21 Withdrawn Training Center North Region Monthly Check
Page 3 of 17
_. ._..m_ . _ . . . _ _ .._..._.. ._ _ _ _ _. - . .._ . . _ _ _ _ _ _.
Attachrnent 2 Response to RAI RegardinD Proposed Technical Specification Chance to Section 6.5.1.6 I I
j PORC
, RECOMMENDED ,
CHANGES TO DOCURIENT ;
REVISION W/ SAFETY -[
PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEF9T (Y/N) '
j t FPP-3.12 2 Fire inspection Power Block
- N N FPP-3.13 2 Fire inspection Non-Power Block
- N N FPP-3.13 3 Fire inspection /Non-Power Block
FPP-3.14 2 Warehouse #2 Sprinkler Test
- N N FPP-3.14 3 Warehouse #2 Sprinkler Test
- N N FPP-3.2 3 Monthly Fire Equipment Check
- N- N FPP-3.24 1 Fire Protection Manifold #6 Sprinkler System N N Main Drain and Water Flow Alarm Test
Main Drain and Water Flow Alarm Test
- FPP-3.25 1 Fire Protection Manifold #5 Sprinkler System N N Main Drain and Water Flow Alarm Test
- FPP-3.25 2 Fire Protection Manifold #5 Sprinkler System N N Main Drain and Water Flow Alarm Test
- Main Drain and Water Flow Alarm Test
Attachment 2 Response to RAI Regarding Proposed Technical Specification Chanoe to Section 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT
~
REVISION W/ SAFETY PROCEDURE NO. NO. . TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
FPP-3.27 1 Fire Protection Manifold #3 Sprinkler System N N Main Drain and Water Flow Alarm Test
- FPP-3.28 1 Sprinkler Nozzle Air Flow Test
- N N FPP-3.29 1 Fire Protection Manifold #2 Sprinkler System N N Main Drain and Water Flow Alarm Test
- FPP-3.3 4 Monthly Hose House Checks * ' N N FPP-3.30 1 Fire Protection Manifold #7 Sprinkler System N N Main Drain and Water Flow Alarm Test
- FPP-3.38 O Annual Portable Ventilation Fan and N N Equipment Check
- FPP-3.8 5 Monthly Fire Extinguisher inspection /Non- -1 N Power Block' ..
ISP-76 11 Fire Protection Carbon Dioxide Instrument N N Calibration
- N N OP-33 27 Fire Protection
- N N OP-33 28 Fire Protection
- N N OP-33 29 Fire Protection
Attachment 2 Response to RAI Regarding Proposed Technical Specification Chance to Section 6.5.1.6 I
PORC RECOMMENDED ;
CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
OP-33 30 Fire Protection
- N N OP-33 31 Fire Protection
- N N RAP-7.1.05D 0 Transfer of Fuel to Alternative Storar,e N N Locations in the Spent Ft,el Foo -
ST-16J1 3 Control Room and Relay Room Emergency N N Lighting Test
- ST-76A 11 Fire Protection System Weekly Checks
- N N ST-76AC 3 East Diesel Fire Pump 76P-4 Operational N N i Check * :
ST-76AG 1 Fire Protection Battery Room Corridor Main N N Drain Test * -
ST-76C 14 West Diesel Fire Pump 76P-1 Operational N N Check
- ST-76D 17 High Pressure Water and Cardox Fire N N Protection System Valve Position Check
- ST-76D 18 High Pressure Water and Cardox Fire N N Protection System Valve Position Check' Page 6 of 17
Attachment 2 Response to RAI Regarding Preposed Technical Specification Chance to Sec; ion 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (YlN)
ST-76E 9 Monthly and Annual Fire Hose Station N N inspections
- ST-76E 10 Monthly and Annual Firo Hose Station N N Inspections
- ST-76E 11 Monthly Fire Hose Station inspections
- N N ST-76F 0 Fire Hose Station Casket inspection and Hose N N Rerack Test
- ST-761 16 Monthly Portable Fire Extinguisher inspection N N Procedure
- ST-761 16 Monthly Portable Fire Extinguisher inspection N N Procedure
- ST-761 17 Monthly Portable Fire Extinguisher Inspection N N Procedure
- ST-76J1 7 Heat Detector Functional Test - EDG Building N N Zone 1 (A and C)* ;
ST-76J1 8 Heat Detector Functional Test - EDG e tilding N N Zone 1 (A and C)*
ST-76J10 13 Heat Detector Functional Tests - HPCI Pump N N ,;
Area
.. .~ . ..
Attachment 2 Response to RAI Regarding Proposed Technical Specification Chance to Section C-5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J10 14 Heat Detector Functional Tests - HPCI Pump N N Area
- ST-76J10 15 Heat Detector Functional Tests - HPCI Pump N N Area
- ST-76J11 12 Heat Detector Functional Tests - RCIC Pump N N Area
- ST-76J11 13 Heat Detector Functional Tests - RCIC Pump N N Area
- ST-76J11 14 Heat Detector Functional Tests - RCIC Pump N N Area
- ST-76J12 9 Heat Detector Functional Test - SGT Filter A* N N
~
ST-76J12 10 Heat Detector Functional Test - SGT Filter A* N N ST-76J13 12 Heat Detector Functional Test - SGT Filter B* N N ST-76J13 13 Heat Detector Functional Test - SGT Filter B* N N ST-76J14 14 Smoke / Heat Detector Functional and CO2 N N Simulated Automatic / Manual Initiation Tests -
North Cable Tunnel
Attachment 2 Response to RAI Regardng Proposed Technical Specification Channe to Section 6.5.1.6 PORC RECOmanangDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/NI BENEFIT (Y/N)
ST-76J15 17 Smoke / Heat Detector Functional and CO2 N N.
Simulated Automatic / Manual Initiation Tests -
South Cable Tunnel
- ST-76J16 15 Smoke / Heat Detector Functional and CO2 N N Simulated Automatic / Manual initiation Tests -
Cable Spreading Room
- ST-76J17 15 Smoke and Heat Detector Functional Tests N N West Electric Bay
- ST-76J17 16 Smoke / Heat Detector Functional and CO2 N N Simulated Automatic / Manual Initiation Tests -
West Electric Bay
- ST-76J18 16 Smoke and Heat Detector Functional Tests - N N East Electric Bay
- 1 ST-76J18 17 Smoke / Heat Detector Functional and CO2 N N Simulated Automatic / Manual Initiation Tests -
East Electric Bay
- ST-76J19 14 Smoke / Heat Detector Functional and CO2 N N Simulated Automatic / Manual initiation Tests -
South Emergency Switchgear Room
- - . . . ._ .. - . . - - . ~ _ - . . ..
Attachment 2 '
Response to RAI Regarding Proposed Technical Specification Chance to Section 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J2 5 Heat Detec*or Functional Test - EDG Building N N Zone 2 (B and D)
ST-76J2 6 Heat Detector Functional Test - EDG Building N N i Zone 2 (B and D)*
ST-76J20 13 Smoke-Heat Detector Functional and CO2 N N Simu!cted Automatic / Manual Initiation Tests -
North Emergency Switchgear Room
- ST-76J21 17 Smoke and Heat Detector Functional Tests - N N Relay Room
- ST-76J21 18 Smoke and Heat Detector Functional Tests - N N Relay Room' ST-76J22 7 Smoke Detector Functional Test - Diesel Fire N N Pumo Room and Radwaste Sample Sink Area
- ST-76J25 5 Smoke Detector Functional Test - Rx Building N N 326' - Southwest
- ST-76J26 8 Smoke Detector Functional Test - Rx Building N N 300' - North
- ST-76J27 5 Smoke Detector Functional Test - Rx Building N N 326' - North'
- - _ . - - - - . . - . .-. - ~ . . . . . . .__- .. - - . . . . .
Attachment 2 Response to RAI Regarding Proposed Technical Specification Chance to Section 6.5.1.6 PORC' RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J28 8 Smoke Detector Functional Test - Rx Bu:Iding N N 300' - South
- ST-76J28 9 Smoke Detector Functional Test - Rx Building N N 300' - South
- ST-76J29 6 Smoke Detecte c unctional Test - Rx Building N N 272'
- ST-76J3 11 Ultra Violet Flame and Heat Detector N N Functional Tests - Recirculation System MG Room
- ST-76J30 S Smoke Detector Functional Test - Rx Building N N g
272' - East
- ST-76J31 7 ~ Smoke Detector Functional Test - Rx Building N N 272' - West
- ST-76J32 5 Smoke Detector Functional Test - East N N Crescent
- ST-76J33 5 Smoke Detector Functional Test - West N N Crescent
- ST-76J33 6 Smoke Detector Functional. Test - West N N
, Crescent *
Attachment 2 Response to RAI Regardireg Pemosed Technical Specification Channe to Section 6.S.1.6 I
PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY ;
PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J34 5 Smoke Detector Functional Test - Rx Building N N ST-76J34 6 Smoke Detector Functional Test - Rx Building N N 344' - Southwest
- ST-76J35 5 Smoke Detector Functional Test - Rx Building N N 344' - North
- ST-76J36 2 Smoke Detector Functional Test - LPCI Battery N N Rooms
- ST-76J36 3 Smoke Detector Functioned Test - LPCI Battery N N ;
Rooms
- ST-76J4 13 West Cable Tunnel Smoke Detector and N N Sprinkler Test
- ST-76J4 14 West Cable Tunnel Smoke Detector and N N Sprinkler Test
- l ST-76J40 5 Smoke Datector Functional Test - Station N N Battery Rooms
- ST-76J40 6 Smoke Detector Functional Test - Station N N Battery Rooms * ,
ST-76J41 3 Smoke Detector Functional Test - Safety N N ,
Pump Rooms t
Page 12 of 17
. _ _ . _ _ _ . ~ . _ _ . . . _ . _ _ _ _ ___ __ ._
Attachment 2 -
Response to RAI Regarding Proposed Technical Specification Channe to Section 6.5.1.6 l
1 1
pg RECOmanerafDED CHANGES TO ,
DOCUMENT REVISION - W/ SAFETY
^
PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J41 4 Smoke Detector Functional Test - Safety N N Pump Rooms
- ST-76J42 3 Smoke Detector Functional Test - Control N N Room Ventilation Rooms
- ST-76J44 2 Smoke Detector Functional Test - Control N N Room Vent Exhaust Ducts
- ST-76J45 5 Heat Detector Functional Test - Water Spray N N Curtain Coundary Number 1
- ST-76J45 6 Heat Detector Functional Test - Water Spray N ,
N Curtain Boundary Number 1
- ST-76J46 5 Heat Detector Functional Test - Water Spray N N .!
Curtain Boundary Number 2*
ST-76J46 6 Heat Detector Functional Test - Water Spray N N Curtain Boundary Number 2*
ST-76J47 4 Heat Detector functional Test - Water Spray N N Curtain Boundary Number 3' ST-76J47 5 Heat Detector Functional Test - Water Spray N N Curtain Boundary Number 3*
Page 13 of 17 9
l Attachment 2 l Response to RAI Regarding Proposed Technical Specification Chance to Section 6.5.1.6 PORC RECOMMENDED CHANGES TO DOCUMENT REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N) A ST-76J48 4 Heat Detector functional Test - Water Spray N N Curtain Boundary Number 4' ,
ST-76J48 5 Heat Detector Functional Test - Water Spray N N Curtain Boundary Number 4' ,
ST-76J49 5 Heat Detector Functional Test - Water Spray N N '
Curtain Boundary Number 5*
ST-76J49 5 Heat Detector Functional Test - Stairwell N N !
Water Spray Boundary Number 5' i
ST-76J5 11 East Cable Tunnel Smoke Detector and N N Sprinkler Test
- ST-76J5 12 East Cable Tunnel Smoke Detector and N N Sprinkler Test * -
ST-76J50 4 Heat Detector Functional Test - Water Spray N N Curtain Boundary Number 6 and 8' ST-76J50 5 Heat Detector Functional Test - Stairwell N N Water Spray Boundaries Numbers 6 and 8*
ST-76JS1 4 Heat De*ector Functional Test - Water Spray N N
- Curtain Boundary Number 7*
Attachment 2 Response to RAI'tegarding Proposed Technical Specification Chance to Section 6.5.1.6 l
l l .
PORC RECOMMENDED CHANGES TO DOCUMENT j REVISION W/ SAFETY PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
ST-76J51 5 Heat Detector Functional Test - Stairwell N N Water Spray Boundary Number 7*
ST-76M 4 Nozzle Air Flow Test for Standby Gas N N Treatment System
( ST-76TD 10 Transformer 71T-3 Deluge Operability Test
ST-76TE 9 Transformer 71T-4 Deluge Operability Test
- N N ST-76U 6 Fire System Flow Test
- N N ST-76Y 13 Fire Door inspection and Operability Test N N ST-76Z 11 Fire Barrier Penetration Inspection and Damper N N Operability Surveillance Test
- i TOP-149 Withdrawal East Loop High Pressure Water Fire Protection N N System Flush
- WACP-10.1.33 5 Hot Work Permits
JAF-RAS-96-OO2 O Fire Suppression Effects Analysis Deficiencies N/A N Page 15 of 17
_ . _ . _ _ . . _ _ , . . . _ . _ . _ . . . . . - _ _ . _ ~ _ _ . __ __ ._ . . _ . _ .._._..._...__.__.._.___._.m.,__ . _ _ _ _ _ . ._ ..
Attachment 2 ,
Response to RAI Regarding Proposed Technical Specif;cE;esi Channe to Section 6.5.1.6 i
i PORC RECORGAENDED CHANGES TO -
N I REVISION W/ SAFETY ,
PROCEDURE NO. NO. TITLE NSE REQUIRED (YM BENEFIT (Y/N) [
JAF-RAS-96-OO2 1 Fire Suppression Effects Analysis Deficiencies N/A N l
JAF-RPT-FPS-02367 1 Fire Protection Plan N/A N i JAF-RPT-FPS-02367 2 Fire Protection Plan N/A N !
i JAF-SE-94-071 1 FSAR Change Request for Storage of QA .N/A N j
! Records !
JAF-SE-94-108 1 Fire Barrier Penetration Seals, Fire Dampers, N/A N and Fire Doors, AP-01.04 Changes JAF-SE-94-108 2 Fire Barrier Penetration Sesis, Fire Dampers, N/A N ;
and Fire Doors JAF-SE-94-132 1 Restoration of the Relay Room System to N/A N .
Normal Mode i JAF-SE-95-045 0 UFSAR Change, Section 9.8.3.9, Drains and N/A N! j Curbs for Fire Protection Water Systems JAF-SE-95-046 1 AP-01.04, Attachment 2 Fire Protection N/A N
l JAF-SE-95-046 2 AP-01.04, Attachment 2, Fire Protection N/A N j Changes :
i
.. o l
l Attachment 2 ~
l Response to RAI Regarding Proposed '
Technical Specification Chance to Section 6.5.1.6 PORC RECOMMENDED ,
CHANGES TO DOCUMENT REVISION W/ SAFETY j PROCEDURE NO. NO. TITLE NSE REQUIRED (Y/N) BENEFIT (Y/N)
JAF-SE-95-067 O Revise Inventory and Extend inspection -N/A N ;
intervals for Exterior Hose Houses and Curb i Valves JAF-SE-96-049 O AP-14.01 and Fire Protection Plan N/A N JAF-SE-96-049 1 AP-14.01 Revision of FSAR Section 9.8.5 & N/A N ,
13.2.1 and Revision to the Fire Protection Plan !
^
JAF-SE-96-049 2 AP-14.01 Revision to FSAR Section 9.8.5 & N/A N 13.2.1 and Revision to the Fire Protection Plan -
l t
P b
o;
+
Page 17 of 17 i