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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:OUTGOING CORRESPONDENCE
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 ML20212F8341999-09-22022 September 1999 Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted 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 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 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 ML20210U2621999-08-12012 August 1999 Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted 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 ML20210A7001999-07-16016 July 1999 Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques 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 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 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 ML20207D9191999-05-27027 May 1999 Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months 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 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 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) 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 ML20205F8031999-04-0202 April 1999 Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants ML20205C1041999-03-26026 March 1999 Forwards Insp Rept 50-333/99-02 on 990125-0209.No Violations Noted.Insp Evaluated Results of Investigation Into Causes of 990114 Hydrogen Fire Event & Licensee Response to Event. Licensee Overall Response to Event,Acceptable ML20204J3791999-03-23023 March 1999 Forwards Insp Rept 50-333/99-01 on 990111-0228.No Violations Noted.Security Program Was Effectively Implemented ML20203E9231999-02-10010 February 1999 Forwards Insp Rept 50-333/98-08 on 981123-990110.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J0571999-02-0303 February 1999 Forwards Safety Evaluation Authorizing Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20202C1871999-01-26026 January 1999 Forwards Request for Addl Info Re Util 971014 Request for Changes to James a Fitzpatrick Nuclear Power Plant TSs to Increase Capacity of Sf Pool.Response Requested within 30 Days of Date of Ltr ML20203H8941999-01-21021 January 1999 Forwards Notice of Withdrawal of Application for Amend to License DPR-59.Amend Would Have Modified TS Re Inservice Leak & Hydrostatic Testing Operations ML20199G7161999-01-19019 January 1999 Informs That NRC Review of Relief Requests Submitted on 980126 for James a FitzPatrick Nuclear Power Plant, Considered Complete ML20198L4041998-12-17017 December 1998 Forwards Insp Rept 50-333/98-07 on 981005-1122 & NOV Re Design Deficiency That Resulted in Main Steam Safety Relief Valve Pilot Solenoid Cables Not Being Installed in Conduit ML20198C2331998-12-15015 December 1998 Ltr Contract:Task Order 236, Review & Evaluation of Fitzpatrick Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198B4531998-12-10010 December 1998 Advises of Planned Insp Effort Resulting from Insp Resource Planning Meeting on 981110.Historical Listing of Plant Issues Encl ML20198F9861998-12-0404 December 1998 Forwards Assessment Re Util 980916 Info Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwr. NRC Agrees with Util Conclusion That Plant Remains within Licensing Basis ML20196J3431998-12-0404 December 1998 Forwards SER Accepting Util Program for Periodic Verification of MOV design-basis Capability at FitzPatrick in Response to GL 96-05 ML20196F9181998-11-25025 November 1998 Forwards Safety Evaluation Re Third 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195K3631998-11-17017 November 1998 Forwards SE Authorizing IST Program Relief Request VRR-05, Per 10CFR50.55a(a)(3)(i) & Relief Requests PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04,per 10CFR50.55a(a)(3)(ii) ML20195D9711998-11-13013 November 1998 Forwards SE Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 ML20195B7331998-11-0505 November 1998 Submits Request for Addl Info Re Proposed Extension of Emergency Diesel Generator Allowed Outage Time ML20155H5251998-11-0303 November 1998 Forwards SE Authorizing Licensee 980508 Request for Relief from Certain ASME Code Requirements at Ja FitzPatrick Npp. Licensee Requested Relief from Requirements for Addl Exams of CRD Bolting When Cracks Detected in head-to-shank Area ML20155H5751998-11-0303 November 1998 Forwards SE Authorizing Proposed Alternative to RPV Shell Weld Exam Requirements of Both ASME BPV Code,Section XI,1989 Edition & Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) for Ja FitzPatrick NPP ML20155B5681998-10-27027 October 1998 Informs That GE Rept GENE-187-30-0598,DRF B13-01920-30, CRD Bolting Flaw Evaluation for Ja FitzPatrick Np, Rev 0,dtd May 1998,submitted by 980507 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20154Q9251998-10-19019 October 1998 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20154Q5111998-10-16016 October 1998 Responds to Re Concerns on Use of Reactor Building Crane to Move Sf with Fuel Pool at Jafnpp.Regrets That Did Not Address Concerns in Satisfactory Manner & Provides Addl Info Re Concerns ML20154L6381998-10-14014 October 1998 Forwards SE Accepting Licensee 980126 Submittal of ISI Program & Relief Requests for Third 10-year Interval for Plant ML20154M0951998-10-14014 October 1998 Forwards Insp Rept 50-333/98-06 on 980824-1004.No Violations Noted.Testing & Control Room Operations Were Conducted Appropriately with Formal Communications ML20154L2371998-10-13013 October 1998 Responds to Util Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, Which Addressed Issues Discussed in 980521 Meeting. Request to Defer Completion of Actions Acceptable ML20154B3951998-09-29029 September 1998 Provides Addl Info Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20154B3421998-09-28028 September 1998 Advises That Info Contained in 980803 Application Re cycle-specific Safety Limit Min Critical Power Ratio for Cycle 14,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20154B8201998-09-28028 September 1998 Forwards Insp Rept 50-333/98-05 on 980727-0814 & NOV Re Failure to Analyze Effects of LOCA Plus LOOP on Containment Penetration Protection ML20153F8791998-09-22022 September 1998 Forwards RAI Re Licensee Response to GL 96-05 for Plant & Indicating Intent to Implement Provisions of JOG Program on motor-operated Valve Periodic Verification ML20153D2551998-09-21021 September 1998 Forwards SE Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B3341998-09-14014 September 1998 Advises That Matl Marked as Proprietary in from Pasn & 980625 Affidavit from Holtec Intl Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-09-09
[Table view] |
Text
_. . _ ._-_ . . . _ _ _ . _ _ _ _ _. . _ _ . . . _ _ _ _ _ _ . - .
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, OEC 171992 Docket No. 50-333 Mr. Harry P. Salmon, Jr.
Resident Manager New York Power Authority James A. FitzPatrick Nuclear Power Plant Post Office Box 41-Lycoming, New ork 13093
Dear Mr. Salmon:
This letter acknowledges receipt of your letter dated September 4,1992, regarding our request.
for information dated August 7,1992.
Thank you for your prompt attention to our request. The information you provided has been reviewed by my staff and_has been determined to be acceptable. .Any further actions with regards to this matter will be pursued through routine inspection activities _
Your cooperation with us is appreciated.
Sincerely,
~
Charles W - Hehl,-Director -
. Division of Reactor Projects
Enclosure:
Letter from NYPA dated September 4,1992 OFFICIAL' RECORD COPY - ' '
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! J. Brons, President l R. Beedle, Executive Vice President - Nuclear
!- G. Goldstein, Assistant General Counsel-i J. Gray, Jr., Director, Nuclear Licensing - BWR
- i. Supervisor, Town of Scriba C. Donaldson, Esquire, Assistant Attorney General, New York Department of Law Director, Energy & Water Division, Department of Public Service, State of New York j K. Abraham, PAO (30) SALP Reports and (2) All Inspection Reports j Public Document Room (PDR) i Local Public Document Room (LPDR)
! Nuclear Safety Infomaation Center (NSIC)
NRC Resident Inspector j State of New York, SLO Designee I
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] W. Cook, SRI - FitzPatrick i G. Tracy, SRI - IP-3 V. McCree, OEDO R. Capra, NRR j' B.' McCabe, NRR i
DRS/EB SALP Coordinator D. Holody, EO R. Fuhrmeisten
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l _ SUBJ ECT : James A. TitzPatrick Huclear Power Plant
- Docket No. 50-333 j Responso'to NRC _ Letter of Allegatien. to Mr. Harry P, Salmon. Jr., dated August 7, 1992 i
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Dear Sir:
i j On August 10, 1992, the New York Power Authority.(NYPA) received the above subject letter, requesting our review and disposition within 30 days of the allegation that some of our fire protection
! systems (sprinkler systems) have been installed by-plumbers and-l pipetitters who were not specifically trained and qualified in
- sprinkler system installation.
[ NYPA has reviewed the Attachment i listing of the fire protection codes and standards from the James A. FitzPatrick Final Safety _
) Analysis Report. This includes those portaining to training and qualification of personnel involved in installation and
{ maintenance of the systems. The primary; codes and standards i portaining to the installation and maintenance are.NFPA 13,__
Sprinkler System Installation; ASME Section IX; ANSI B31.1, Power l
l Piping; and American Welding Society ~(AWS) Codes D1.1 and D10.9.
i j During the present outage, only two modifications involving i installation of sprinklers within the power-block were performed-i at the James-A. FitzPatrick Nuclear Power Plant, M1-91-205, l Battery Corridor Suppression System, and F1-92-109, Cable Tunnel Fire Protection.
To date, all mechanical work acsociated with the installation of piping-for the subject modifications has'been performed by
[ journeyman and apprentico sprinkler fitters represented by:
l Road Sprinkler Fitters Local Union No. 669, Landover,
- Mr.ryla nd , of the United Association of Journeyman and-Auprentices of the Plumbing and Piperitting Industry of the United States and Canada l ,
I
'h C )
f U.S. Nuclear Regulatory Commission September.4, 1992
SUBJECT:
RESPONSE TO HRC LETTER OF ALLEGATION JAFP 0635 TO MR, HARRY P. SALMON, Page QAIED AUGUST 7. 1992 I
sprinkler Fitters are skilled in the follouing areas:
J Installation of overhead piping Installation of system control valvet Installation of control devices and i i u ms Installation of supply system Repair and remodeling work NYPA Construction Services does not employ plumbers to l install modifications.
Cer inkler Fitter Welders aro certified to ASME Section IX and AWS D1.1 in accordance vith the JAF Site Welding Program. NFPA 13 references AWS D10.9 Quality Level AR-3; this level'of quality-was attained by use of the JAF Site Welding Program. Also, pipefitters, although they did not work on the subject modifications, are also certified to the above ASME Section IX and AWS D1.1 codes.
Additionally, Quality Assurance provisions have been established for the design, procurement, installation, testing, and administrative controls of fire? protection within the plant.
Activities related to fire protection are performed in accordance with the quality assurance requirements of Appendix A to-BTP 9.5-I within the applicable provision of the-Quality Assurance Program predicated on Appendix B to 10 CFR 50.
Therefore, based on the above, NYPA believes that we have met our commitments pertaining to installation and maintenance of the fire protection-sprinkler systers. -
This response contains no personal privacy, proprietary, or-safeguards information and can be-released-to the-public and -
- .placed in the NRC Public Document-Room.
Should you have additional questions on the above, please contact us.
Very truly yours,:
'. ,g
/,
z.i
, i j/;w- /y-,/ :.;l'Nd .
' HARRY P.' SALMON, JR.d RESIDENT MANAGER Attachment HPS:AA:nrb cc: See next-page
ATTACHMENT 1 The, equipment and systems are inspected and tested upon
installation in accordance with the following Standards of the tutional Fire Protection Association and the recommendations and requirements of the American Nuclear Insurers.
e NFPA 1201 -
Organization for Firo Services NFPA 6 -
Industrial Fire Loss Provention
. NFPA 7 --
Management of Firo Emergencies NFPA 10 - Portablo Fire Extinguishers NFPA 11 - Foam Extinguishing System NFPA 12 - Carbon Dioxido System I NFPA 13 -
Sprinkler System Installation NFPA 14 -
Standpipe and Hose Systems NFPA 15 -
Water Spr,ay Fixed Systems NFPA 19B -
Respiratory Protectivo Equipment for Firefighters NFPA 20 -
Centrifugal Firo Pumps NFPA 24 -
Outside Protection NFPA 26 -
Supervision of Water Supply Valves NFPA 27 -
Private Firo Brigades NFPA 30 -
Flammable and Combustible Liquids Code NFPA 49 -
Hazardous Chemicals Data NFPA SOA -
Gascous Hydrogen Systems 4
NFPA 51B -
Cutting and Welding Process NFPA 70 -
National Electric Code NFPA 72D -
Proprietary Signaling Systems NFPA 72E -
Automatic Fire Detectors NFPA 78 -
Lightning Protection Codo NFPA 80 -
Fire Doors and Windows NFPA 196 -
Fire Hose
, NFPA 251 -
Fire Tests, Building Construction and Materials Fire Protection Handbook (NFPA) -
XIV edition Underwriter's Laboratories, Inc. -
Fire Protection Equipment List American Society for Testing and Materials -
Material Designation ANSI Standard B31.1 Power Piping American Society of Mechanical Engineers -
Unfired Pressure Vessel Code - VIII Factory Mutual Approval Guide Appendix A -
APCSB 9.5-1 4
- - - , , - . ~ ,
p,c : Regional Administrator Nuclear Regulatory Commission
. U.S.
475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabe Project Directorate I-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 l
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