ML20059M915
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| ML20059M915 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, FitzPatrick  |
| Issue date: | 06/13/1990 |
| From: | Hickman D NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 9010050361 | |
| Download: ML20059M915 (1) | |
Similar Documents at Indian Point, FitzPatrick | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1851999-10-19019 October 1999
[Table view]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 ML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 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 ML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 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 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 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 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 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 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager 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 ML20211H6291999-08-26026 August 1999 Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3 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 ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20210U2621999-08-12012 August 1999 Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr 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 ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium 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 ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager 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 ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls 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 ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 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 ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl 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 1999-09-09 Category:NRC TO UTILITY MONTHYEARML20058H1991990-11-0707 November 1990
[Table view]Grants Temporary Waiver of Compliance W/Ts 3.7.D.2 & 3.7.D.3 Re Mod to Isolate Reactor Coolant Sample Line.Temporary Waiver Authorized Because solenoid-operated Containment Isolation Valve Safety Significance Low ML20062D1561990-11-0505 November 1990 Forwards Understanding of Unimplemented Gsis,Per Licensee 900703 Response to Generic Ltr 90-04.Timely Completion of Listed GSIs Encouraged ML20058B7081990-10-18018 October 1990 Forwards Insp Rept 50-333/90-06 on 900812-0922 & Notice of Violation ML20062B9251990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B7681990-10-11011 October 1990 Responds to Re Complement of Candidates for Simulator Exams Administered as Part of Initial Licensing Process ML20062A0351990-10-0909 October 1990 Advises That 900611 Rept GE11 LTA Fuel Bundle Description Rept for PASNY Ja Fitzpatrick Nuclear Power Plant, Withheld from Public Disclosure IR 05000333/19900041990-10-0909 October 1990 Forwards Results of 900821 Enforcement Conference to Discuss Violations Noted in Insp Rept 50-333/90-04 ML20062A0821990-10-0202 October 1990 Ack Receipt of in Response to 900606 Notice of Violation.Determined That Violation Involving Failure of PORC to Review Implementing Radiation Protection Procedures, Remain as Originally Cited ML20059K4231990-09-13013 September 1990 Forwards Safety Evaluation Re IGSCC Insp & Repair for Facility Reload 8,Cycle 9 Refuel Outage Based on Review of Submittals ML20059L2131990-09-0404 September 1990 Forwards Insp Rept 50-333/90-05 on 900701-0811 & Notice of Violation ML20056B3941990-08-20020 August 1990 Forwards Safety Evaluation Granting Relief Request R14 & Denying Requests R15 & R5A Re Second 10-yr Interval Inservice Insp Program,Per 10CFR50.55a(g)(6)(i) ML20059A4151990-08-17017 August 1990 Forwards List of Topics for Discussion During Planned Site Visit Re Hardened Wetwell Vent at Facility.No Conclusions Will Be Reached During Site Visit ML20058P4281990-08-13013 August 1990 Forwards Safety Evaluation Accepting Modified Recirculation Pump Trip (RPT) Logic Design & Alternate Rod Insertion/Rpt Logic Testing Features Based on Review of 900423 Submittal ML20056A9361990-08-0606 August 1990 Forwards Insp Rept 50-333/90-04 on 900527-0630.No Violations Noted ML20058N0621990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Encouraged to Start Similar Initiative to Provide for Sharing of Info & Experiences Involving Engineering & Solutions of Problems Common to All ML20058L8141990-08-0606 August 1990 Discusses Util Response to Notice of Violation & Proposed Imposition of Civil Penalty.Sufficient Basis Not Provided for Adjustment in Civil Penalty Amount ML20056A8291990-07-26026 July 1990 Forwards Maint Insp Tree,Inadvertently Omitted from 900716 Maint Insp Rept 50-333/90-80 ML20055J3361990-07-19019 July 1990 Forwards Outage Completion Team Insp Rept 50-333/90-81 on 900604-08.Util Mgt Controls,Programs & Personnel Were Adequately Completing Items Necessary to Support Plant Restart.Several Minor Problems Identified During Insp ML20055G3761990-07-16016 July 1990 Forwards Maint Team Insp Rept 50-333/90-80 on 900416-0511. Violation Noted But Not Cited ML20055E0671990-07-0303 July 1990 Accepts Util Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20055F6101990-06-29029 June 1990 Requests Util Provide Ref Matls Listed in Encl for Reactor Operator & Senior Reactor Operator Licensing Exam Scheduled for Wk of 901029 ML20055D0491990-06-26026 June 1990 Forwards Insp Rept 50-333/90-03 on 900426-0526.No Violations Noted.Nrc Concerned W/Increase in Frequency of Personnel Errors & Poorly Documented 10CFR50.59 Decision Prior to Implementation of Control Room Human Factors Design Mods ML20055E3031990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20059M9151990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20059M9111990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G9521989-10-0202 October 1989 Forwards FEMA to DA Devito Re Inadequacies During 890516 Emergency Exercise at Plant ML20248G7351989-09-25025 September 1989 Forwards Corrected Page 3 of Insp Rept 50-333/89-19 to Replace Page 3 of Rept Submitted w/890914 Ltr ML20248C4321989-09-25025 September 1989 Forwards Amend 23 to Indemnity Agreement B-19,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701.Util Requested to Submit Signed Amend to Signify Acceptance ML20248D2241989-09-25025 September 1989 Forwards Amend 9 to Indemnity Agreement B-63,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements. Util Requested to Submit Signed Amend to Signify Acceptance ML20247M9731989-09-14014 September 1989 Forwards Insp Rept 50-333/89-19 on 890905-07.No Violations Noted.Emergency Response Actions Adequate to Provide Protective Measures for Health & Safety of Public ML20247K5971989-09-0808 September 1989 Forwards Safety Insp Rept 50-333/89-16 on 890710-14.No Violations Noted.Corrective Actions for Four of Five Violations Addressed Found to Be Acceptable.Revised Procedures Needed in Area of Commercial Grade Items ML20247B9451989-09-0606 September 1989 Forwards Enforcement Conference Rept 50-286/89-15 on 890808 ML20246L6611989-08-30030 August 1989 Forwards Safety Insp Rept 50-333/89-17 on 890731-0804.No Violations Noted.Mobile Lab Brought to Site & Used to Make Independent Measurements to Verify Capability for Analyzing Radioactive Effluents & to Achieve Methods of Analyses ML20246K4921989-08-25025 August 1989 Forwards Insp Rept 50-333/89-18 on 890724-28.No Violations Noted ML20246K5271989-08-23023 August 1989 Forwards Safety Insp Rept 50-333/89-15 on 890717-21.No Violations Noted ML20246F7311989-08-22022 August 1989 Forwards Safety Sys Functional Insp Rept 50-333/89-80 on 890501-26 & Notice of Violation.Mgt Attention Should Be Given to Listed Areas,Including Effects of Over Voltage on 600-volt Motor Control Ctrs ML20246C4171989-08-17017 August 1989 Forwards Safeguards Insp Rept 50-333/89-14 on 890710-14.No Violations Noted ML20246B0111989-08-11011 August 1989 Forwards Insp Rept 50-333/89-08 on 890604-0729.No Violations Noted ML20248A5831989-08-0202 August 1989 Forwards Radiological Controls Insp Rept 50-333/89-13 on 890613-15 & Notice of Violation.Unplanned Exposures Suggest Lack of Effective Mgt Oversight of Radiologically Significant Spent Fuel Pool Work Activities ML20247R0751989-07-28028 July 1989 Forwards Safeguards Insp Rept 50-286/89-15 on 890605-07. Enforcement Conference Scheduled on 890808 to Discuss Previous Concerns Re Implementation of Security Program & Weaknesses in Protected & Vital Area Barriers ML20247J8311989-07-19019 July 1989 Forwards Amend 142 to License DPR-26 & Safety Evaluation. Amend Adds Surveillance Requirement to Tech Spec 4.16 Requiring Periodic Leak Testing of Low Head Injection Line Check Valves 897A-D & RHR Check Valves 838A-D ML20247C1311989-07-14014 July 1989 Provides Emergency Exercise Objectives & Scenario Guidelines to Be Used During Emergency Exercise Scheduled for Wk of 891113 ML20246F9341989-07-0707 July 1989 Forwards Requalification Program Evaluation & BWR Power Oscillation Program Insp Rept 50-333/89-04(OL) on 890501.All Six Reactor Operators & Six Senior Reactor Operators Passed Exam.Two Senior Reactor Operators Failed Written Exam ML20245J8681989-06-23023 June 1989 Forwards NRR Director to Ecology Ctr of Southern California Representative Acknowledging Receipt of Petition Filed by Ctr & Advising That Petition Being Treated Under 10CFR2.206 of Commission Regulations ML20245F0151989-06-21021 June 1989 Forwards Request for Addl Info Re LPCI Pump Flow Surveillance Amend Based on Review of 890531 Tech Spec Amend Request ML20245G5411989-06-21021 June 1989 Forwards Request for Addl Info Re 890531 Application for Amend to Tech Specs on Core Spray Sys Surveillance ML20245E7231989-06-16016 June 1989 Forwards Insp Rept 50-333/89-07 on 890419-0603.No Violations Noted ML20244C9041989-06-12012 June 1989 Grants 880729 Request to Withhold JPTS-88-016, Proposed Change to Tech Specs Re Reload 8/Cycle 9 (JPTS-88-016), from Public Disclosure Per 10CFR2.790 ML20248C0941989-06-0505 June 1989 Forwards Amend 141 to License DPR-26 & Safety Evaluation. Amend Adds Surveillance Requirement to Tech Specs Requiring Periodic Testing of Backup Nitrogen Supply Sys for Operating PORVs 1990-09-04 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M1851999-10-19019 October 1999
[Table view]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 ML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20212F8341999-09-22022 September 1999 Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted 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 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 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager 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 ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls 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 ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl 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 ML20204J9971999-03-0909 March 1999 Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted 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) ML20202J6171999-02-0505 February 1999 Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning 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 ML20198E9561998-12-21021 December 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees 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 ML20198C2371998-12-15015 December 1998 Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198C3251998-12-11011 December 1998 Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt 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 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 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 ML20155H2901998-11-0303 November 1998 Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided 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) ML20154Q1761998-10-21021 October 1998 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7) 1999-09-09 |
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- * .# roto 'o UNITED STATES
- - ~g I" c NUCLEAR REGULATORY COMMISSION g E W ASHING TON. D. C. 20055 s
"% , , , , , +j June 13, 1990 Mr. John C. Brons Executive Vice President-Nuclear Generation Power Authority of the State of New York 123 Main St.
White Plains, NY 10601 Dear Mr. Brons The Nuclear Regulatory Commission's Performance Indicator Program provides eight performanco indicators for use by NRC senior managers to monitor trends in the overall performance of individual
( nuclear power plants. These indicators provide an additional view of operational performance to supplement that obtained through other NRC programs. The purpose of this letter is to transmit to you the NRC performance indicators for James A. Fitzpatrick Nuclear Power Plant and Indian Point Nuclear Generating Station, Unit 3 for the first quarter of 1990. I have also included Announcement No.
200 on the use of performance indicators and the definitions of the indicators, which are contained in each issue of the report.
You will routinely be sent a copy of future quarterly performance indicators for Fitzpatrick and Indian Point, Unit 3.
If I can be of any further assistance, you may contact me at (301) 492-4361.
Sincerely, Donald E. Hickman, Chief Performance Indicators Section Office for Analysis and Evaluation of Operational Data U.S. Nuclear Regulatory Commission
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