|
---|
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 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 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-99-026, 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 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 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 05000333/LER-1999-003-01, Forwards LER 99-003-01 Re SRV Setpoint Drift.Revised Rept Is Being Submitted to Change Commitment Due Date Made in Original LER1999-06-28028 June 1999 Forwards LER 99-003-01 Re SRV Setpoint Drift.Revised Rept Is Being Submitted to Change Commitment Due Date Made in Original LER 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 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 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-99-0127, 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-99-0125, 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 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) 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H1991990-11-0707 November 1990 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 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 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 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 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 ML20044A7791990-06-26026 June 1990 Forwards Safety Insp Rept 50-333/90-18 on 900604-08.No Violations Observed.Use of Shipping Cask Gasket Beyond Expiration Date Categorized as Noncited Violation 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 ML20044A5451990-06-18018 June 1990 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 900801 in King of Prussia,Pa to Discuss Recent Changes in Format for Requalification/Initial Exams. Proposed Agenda & Lodging Info Encl ML20044A0461990-06-18018 June 1990 Confirms Dates of 900625-29 for Scheduled Reg Guide 1.97 Insp.Requests That Listed Documents Be Provided During Insp ML20055E3031990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20043G6651990-06-13013 June 1990 Advises That Reactor Vessel Head Has Sufficient Fracture Toughness to Preclude Fracture of Head W/Flaws Remaining in Component & Head Acceptable for Continued Svc for at Least One Addl Fuel Cycle,Per 900525 Analysis Rept ML20059M9151990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043F8011990-06-12012 June 1990 Advises That Facility Can Be Safely Returned to Operation for One Addl Operating Cycle W/Assurance That Integrity of Reactor Coolant Pressure Boundary Will Be Maintained,Per Evaluation of IGSCC Insp ML20043E6591990-06-0606 June 1990 Forwards Radiological Controls Insp Rept 50-333/90-17 on 900505-11 & Notice of Violation ML20034D0021990-05-23023 May 1990 Forwards Safeguards Insp Rept 50-333/90-16 on 900423-27.No Violations Noted ML20043B5541990-05-22022 May 1990 Forwards Draft Info Notice to Region I Reactor Licensees Advising That Assessing Intakes of Radioactive Matl Using Bioassay Data Should Be Based on Best Data & Models Available for That Purpose ML20043B3671990-05-21021 May 1990 Forwards Final SALP Rept 50-333/88-99 for May 1988 - Sept 1989.List of Attendees Also Encl ML20043B0301990-05-18018 May 1990 Forwards Info Re Outstanding Issues from Safety Evaluation Supporting Amend 120 to License DPR-59 Re Reliability of Manual Bus Transfers Between Onsite & Offsite Power Supplies.Meeting Requested to Discuss Outstanding Issues ML20043B3111990-05-18018 May 1990 Forwards Safety Insp Rept 50-333/90-14 on 900402-06.No Violations Noted ML20042G7511990-05-0909 May 1990 Forwards Insp Rept 50-333/90-02 on 900312-0425 & Notice of Violation.Violation Involves Failure to Perform Adequate Survey Prior to Refuel Floor Work ML20042G0221990-05-0808 May 1990 Advises That Encl Notice of Consideration of Issuance of Amend to OL & Opportunity for Hearing Forwarded to Fr for Publication.Amend Re Safety Relief Valve Performance Limits. W/O Encl ML20042G0161990-05-0404 May 1990 Forwards Notice of Denial of Amend to License & Opportunity for Hearing Re Proposed Change to Tech Spec 4.6.F.2 to Eliminate Augmented Inservice Insp of Main Steam & Feedwater Piping Welds ML20043A9071990-05-0202 May 1990 Forwards Agenda for NRC Region I Radiation Protection Managers Conference on 900523-24 in King of Prussia,Pa. Agenda Items Include,Exposure Controls,Radiological Consequences of Unexpected Crud Bursts & Prenatal Exposure ML20034C3641990-04-27027 April 1990 Advises That Util 890721 Response to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning Acceptable. Issue Complete for Plant & TAC 73485 Closed ML20042F3271990-04-26026 April 1990 Forwards Safety Insp Rept 50-333/90-15 on 900409-13.No Violations or Deviations Noted ML20034B7961990-04-23023 April 1990 Forwards Enforcement Conference Rept 50-333/90-12 on 900409 ML20034B0991990-04-18018 April 1990 Advises That 891214 Request for Exemption from Analog Trip Unit Diversity Requirements for ATWS Premature & Unnecessary at Present Time.Nrc Awaiting Description of Mods Before Acceptability Can Be Determined ML20034A9001990-04-13013 April 1990 Forwards Safety Insp Rept 50-333/90-13 on 900220-0302 & Notice of Violation.Insp Covered Fire Protection Program & Related Activities.Ack Receipt of Re Findings of SSFI Conducted by NRC in May 1989 ML20034B3931990-04-12012 April 1990 Forwards Insp Rept 50-333/90-01 on 900125-0311 & Notice of Violation ML20034A5301990-04-11011 April 1990 Advises That Util 900129 IGSCC Insp Plan for 1990 Refueling Outage Re Reduction of Welds Meets Guidelines of Generic Ltr 88-01 & Acceptable ML20012E8221990-03-28028 March 1990 Forwards Safety Evaluation Accepting Util 890630 Response to Generic Ltr 88-11, Radiation Embrittlement of Reactor Vessel Matls. Proposed Pressure Temp Limit Curves Acceptable ML20012E9011990-03-26026 March 1990 Accepts Util Response as Fulfilling Requirement of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Addl Info Confirming Implementation of Actions, Expected within 30 Days of Implementation ML20034A1551990-03-19019 March 1990 Advises of Radiation Protection Managers Conference Scheduled for 900523-24 in King of Prussia,Pa to Exchange Info on Issues of Mutual Interest Re Power Reactor Radiological Controls Programs ML20012C9201990-03-19019 March 1990 Advises That Schedule for Performing First 10-yr Insp Interval Inservice Insps Acceptable,Per Util ML20012D7331990-03-15015 March 1990 Forwards Insp Rept 50-333/89-12 on 891203-900124.Violation Noted But Not Cited.Insp Identified Need to Improve Onsite Communications 1990-09-04
[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 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 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 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 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 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 ML20154L6381998-10-14014 October 1998 Forwards SE Accepting Licensee 980126 Submittal of ISI Program & Relief Requests for Third 10-year Interval for Plant 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 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 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 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] |
See also: IR 05000333/1985013
Text
.
'
fo
.
NOV 2 5 1985
Docket No. 50-333
,
Power Authority of the State of New York
James A. FitzPatrick Nuclear Power Plant
ATTN: Mr. Radford J. Converse
Resident Manager
P. O. Box 41
Lycoming, New York 13093
Gentlemen:
Subject:
Inspection No. 50-333/85-13
This refers to your letker dated October 1,1985, in response to our letter
dated August 14, 1985.
Thank you for informing of the status of the actions you have initiated in
response to the assessment conducted during NRC Inspection No. 50-333/82-24.
We found this status generally acceptable and responsive to our concerns.
While you have completed a majority of the actions associated with (1) Compre-
hensive Planned Maintenance Program, (2) Review of Records in the Vault for
Retention, (3) Indoctrination and Training Program Development for Technical
Services Personnel and (4) Qualification Standards for Maintenance Personnel,
we notice that these actions will not be fully completed until 1986 or there-
after. We expect that you would track and complete these actions as stated.
Should it become apparent that any of these actions cannot be completed as
stated, please inform us immediately of (1) the reasons for not completing
these actions as stated, (2) detailed milestones for completion of the actions
,
and (3) management controls established to complete future quality affecting
activities in a timely and an acceptable manner.
Your cooperation with us is appreciated.
.
Sincerely,
9risinal 51sne W:
A J[!
4 Stewart D. Ebneter, Director
Division of Reactor Safety
8512090377 e51125
PDR
ADOCK 050
33
/
h
0FFICIAL RECORD COPY
RL FITZ 85-13 - 0001.0.0
11/21/85
. _
.-
.
-
..-
.__
~
.
-
.
o'
.
Power Authority of the
2
State of New York
cc:
L. W. Sinclair, President
J. P. Bayne, First Executive Vice President and Chief Operations Officer
A. Klausmann, Vice President - Quality Assurance and Reliability
,
R. L. Patch, Quality Assurance Superintendent
George M. Wilverding, Chairman, Safety Review Committee
Gerald C. Goldstein, Assistant General Counsel
i
NRC Licensing Project Manager
De'pt. of Public Service, State of New York
Public Document Room (PDR)
.
Local Public Document Room (LPDR)
'
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of New York
'
bec:
Region I Docket Room (with concurrences)
Management Assistant, DRMA
Section Chief, DRP
,
4
,
!
!
i
l
.
(
RI:DRS
R
S
RS
R
Oliveira/ms
Eapen
Bettenhausen
Ebneter
11/
85
11/
85
11
/85
11
0FFICIAL REC
COPY
RL FITZ
- 0002.0.0
11/19/85
.
- - - -
_ . _ - - - ,
e
-
.e,.
,
m
, -
r-,
r-
+y-
gm.-,
. , - - -
--
--r-
,m=
v
--nw- - ,-
s~ . -
,,---y
, - -
- ,,
-
.
-
-
_.
-
,
- .
.
.
_
--
'*
'f
_
.-
-
Jemen A. FitiP: trick
-
'
^
Nuclear Power Plant
PO. Box 41
,
Lycomeng. New York 13093
-
315 342.384o
Radford J. Converse ;
4 hMo&h
" ' ' * " ' ' " " '
4# Authority
,
October 1, 1985
JAFP 85-0781
Mr. Stewart D. Ebneter, Director
Division of Reactor Safety
U. S. Nuclear Regulatory Commission
Region i
I
631 Park Avenue
!
King of Prussia, PA 19406
'
,
,
Subject :
James A. FitzPatrick Nuclear Power Plant
(
Docket No. 50-333
Inspection Report No. 50-333/85-13
{
Reference:
NRC Operational Assessment Team inspection
!
(No. 50-333/82-24)
,
,
Dear Sir:
!
In response to your request in the subject inspection, the Authority
I
is providing a status of the actions initiated in response to
i
concerns identified in the referenced NRC Assessment. As noted in
Item 4.4 of Inspection 85-13, a Quality Assurance Department Audit
was performed to review each action item. This audit (Surveillance
Audit No. 1029, dated July 22, 1985) provided a status of all
responses to concerns identified in the referenced inspection and
y
,
provided management with an updated status and recommendations to
complete any open items. A copy of the QA Audit was also provided
,
i
to the NRC Resident inspector.
i
Attachment I of this letter shows the current status of all items
which were identified in Appendix B of the referenced inspection.
Detailed observations which were utilized to derive the status shown
in Attachment I are contained in QA Surveillance Audit No. 1029
'
In addition to items specifically identified in Appendix B of the
!
referenced inspection, this response also addresses the status of two
i
other concerns addressed in open item 85-13-02 of the subject
!
Inspection. These items were also addressed in QA Surveillance Audit
No. 1029
The present status of these items is addressed in
Attachment 11 of this letter.
Very truly yours,
tw
gy
RADFORD J. CONVERSE
RJC:WF: fah
t
.
.n.
.-
.?
(c. ew x m nn,
rt
.
.
- .
. _
.
_-.
. - .
.
.
. -
.
.. .
-
- . .
. - - .- -
- --
-
.
- -
__
-
-e
-
- - -
, '*
-
. _ -
~
-
,-
.-
,
._.
.
-
,
_.
_ _ _
.-
.
-
,
__
__
--
.
.
_
-
..
.
Mr. Stewart D. Ebneter, Director
October 1, 1985
-
_U. S. Nuclear Regulatory Commission
JAFP 85-0781
From:
Radford J. Converse
Page 2 of 2
Subject: -Inspection Report 50-333/85-13
Distribution:
J. C. Brons: NYPA: WPO
R. A. Burns: NYPA: WP0
R. E. Beedle: NYPA: WP0
J. Gray: NYPA: WP0
G. Wilverding: NYPA: WPO
A. Klausmann: NYPA: WPO
W. Fernandez: NYPA: JAF
R. Patch: NYPA: JAF
i
NRC Resident inspector
NRCI 85-13 File
Document Control Center
.
e
i
1
CERTIFIED NAll - RETURN RECEIPT REQUESTED
r
4 -
- . _ . - - ._ - . , - - , _ - . _
.- .-
. . , _ . . ,
, , . .
_ . _ . , . . . . . . . _ . . ,
, . . . . . , _ .
. . . _ , , . . _ .
.
_ . .
.
... . _ . . . _ _ -
.
-
__
._
. _..
-
-
. _ . .
_ _ .
_
-
-
.'
-
- ' -
.
.
..
= . _
,
. _
.
-
_
.-
ATTACHMENT l
~
,
INSPECTION
NO.
FINDING
ITEM
STATUS
1
A.I.a
Revise D&A procedures 3.11
Complete
and 3.18.
2
A.I.b
Provide design verification
Complete
for modification F1-31-2G.
3
A.I b
Issue new set of Revision 1
Conplete
4
calculations as required
by EDP-2.
4
A.I.b
Provide training to PE
Complete
section on 10 CFR 50 App. B
and ANSI 45.2.11.
5Property "ANSI code" (as page type) with input value "ANSI 45.2.11.</br></br>5" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process.
A.I.c
Provide correct design
Complete
verification for modification
<
F1-80-20.
6
A.I.d
Provide forms and procedures
Complete
'
for recording phone calls
and meetings.
7
A.1.d
issue procedures to cover
Complete
. activities of Project
'
Engineering - BWR.
8
B
Review and mark up NuAPs
Complete
and NGPs.
9
B
Issue final revised NuAPs,
Complete
l
NGPs and new procedures.
10
C.I.a
Write Maintenance Department
Closed in
'
procedures and policies, and
Inspeccion
issue administrative manual.
84-08.
I
11
C.I.b
Complete Maintenance
Closed in
Department hiring to fill
Inspection
i
open positions.
84-08.
'
12
C.I.c
issue and implement ITP
Closed in
.
procedure for training of
Inspection
,
i
maintenance contractor
84-08.
[
personnel.
13
C.I.d
Hire Contract Services Engr.
Closed in
i
!
Inspection
'
'
84-08.
[
14
C.2.a
Obtain or create computerized
Complete
'
,
PM scheduling program.
.
k
.t
. _ . ,
.
- , - .
.-.--
.- , ~ - , . .
-
, - . - -.., . . . . , . - , . - ,
. -
- - , . . , , . ..-
. - . - - ,
~
-
w-
-
-
-.
-
.. :
-
_
_
_
_
.
-
.-
_
._
--
--
,
_ _
-
-
_
. . _
ATTACHMENT I
.
INSPECTION
NO.
FINDING
ITEM
STATUS
15
C.2.b
Develop a procedure to
Complete
administer PM program.
16
C.2.c
Incorporate plant components
See Response
into PM program.
Update A.
17
C.2.d
Assure that 40% of Maintenance
See Response
activities are preventive.
Update A.
18
D.I.a
Supplement present site QA
Complete
audit program.
19
D.I.b
Coordinate audit of site fire
Complete
protection activities.
20
D.I.b
Expand utilization of
Complete
technical expertise from
other organizations.
21
D.2
Revise QA procedures manual.
Complete
22
D.2
Develop and implement QA
Complete
procedures for Design Control .
23
D.3
Develop internal audit
Complete
schedule.
24
E.1, E.2
Revise plant and HQ
Complete
administrative records
management procedures.
25
E.2
Complete records retention
Complete
index for HQ and plant.
26
E.2
issue final version of nuclear
Complete
records retention schedule.
27
E.3
Complete archival records
Complete
vault.
28
E.3
Complete archival records
See Response
retention program.
Update B.
29
F.1
Develop lesson plan for
See Response
Tech. Services personnel.
Update C.
30
F.1
Revise l&T procedures to
Closed in
meet INP0 guidelines.
Inspection
84-12.
.
-
-
-
. - -
-
_
_
--m_
_
-
.-
-
-
_
.
-
_
ATTACHMENT I
INSPECTION
NO.
FINDING
ITEM
STATUS
31
F.1
Revise training procedure
Closed in
for HQ personnel .
Inspection
84-12.
32
F.1
Complete qualification
See Response
standards and cards for
Update D.
maintenance personnel.
33
F.1
Commence skill and
Closed in
plant-specific training.
Inspection
84-12.
,
_.
-
-
- t
..
x
,
-
- - .
-
<
./
.-
,
__
__
-
.
. .
-
-
-
7
. .
- -
-
.
.
_
---
_
ATTACHMENT I
~
,
RESPONSE UPDATE - A
4
As noted in C.2.a and C.2.b of this attachment, a computerized P.M.
Scheduling Program has been developed and an administrative P.M.
j
program procedure has been approved and implemented,
i
in 1984 a Task Force, including site and corporate personnel, was
i
constituted to develop the basis for a comprehensive planned
maintenance program. This effort was completed and a short term
!
and long term p;an has been developed for implementation. Currently,
plant procedures are being upgraded to provide detailed direction for
the maintenance of safety-related components.
Formalized preventive
maintenance is currently scheduled and being performed on safety-related
breakers, motor control centers, switchgear and safety-related
<
,
limitorque operators which can be taken out of service during plant
j
operation. A schedule for the maintenance of safety-related limitorques
,
j
requiring an outage is being developed. When completed, an estimate of
{
resources necessary to support that schedule will be made and action
taken to procuse these resources. A program and schedule for repacking
important safety-related valves is also being developed for completion
,
,
by the end of the year. The formalization of the lubrication program
!
will be completed by 1/31/86 for important plant equipment. The PM
!
program will be expanded from this scope in accordance with our lo'ng
term plan and budgetary restraints.
l
A contract award to institute a computerized vibration monitoring
program has just recently been issued, and implementation is scheduled
throughout 1986,
i
While the goals established in C.2.c and C.2.d have not been completely
met, the Authority believes that sufficient progress has been made to
1
close out these i tems of Inspection 84-24.
i
RESPONSE UPDATE - B
The records storage facility has been complete and is in full operation.
However, at the present time, the records being maintained in the vault
- '
are being reviewed to determine which records can be purged and what
the proper retention schedule is for the remaining records. A contractor
j
has been hired to assist in this effort.
i
i
,
RESPONSE UPDATE - C
'
1
Formal training in the areas of design verification, technical review of
procurement documents, equipment qualification and other technical areas
has been provided. .The Authority, however, does recognize the need for
,
a structured-program which addresses the continuing training of Technical
!
Services' Engineers and a JAF Indoctrination and Training Procedure for
Technical _ Services Department personnel (ITP-17) will be implemented by
January 1, 1986,
t
!
,
,o
g y y e w.4-p-.%-i,-r-+
pfy.-+-i--,
31g---wg- y
ym.e'7g'
g-.9=--ipqgag-p
'*-
-=w*-T--?*T**--"* * ' '
p*peM**'G---P"vy'*'
m-A*"w+e+=d'We*=We
' * ***
d
9"-8'"9
F--
1
'D"+"fTf*"'WWW448TWe'P9--""'W"T9"W-2
'
-
_
-
_
_
_
-
_- 2 _ :
_
_
_
..
,
-
__
_
._3
-
-
~
..
ATTACHMENT I
.
RESPONSE UPDATE - D
Implementation of the last phase of the apprentice program will commence
by February, 1986. All phases with the exception of on-the-job training
are presently being implemented.
,
L
m
_
__
_
-_
7
_
_
- . .
__
~
-
.
-
_
-
_
-
,
_
_
.
ATTACHMENT ll
4
Concern:
NRC inspection 85-13, open item 85-13-02, states "In
response to another 0AT concern, the licensee provided a draft
revision to the Plant Standing Order (P50) No. 5 fci the NRC
review. This draft revision contained measures to provide better
on-site control for the drawings and records.
However, this draf t
was never formally issued."
Response:
Two plant procedures will be issued to replace PS0 No. 5
These procedures for Plant Drawing Control and for the Control of
Vendor Technical Manuals, will be issued by October 31, 1985
Concern:
Page 8 of Inspection 85-13, item 85-13-02 states:
The inspector verified the status of resolution for the drawing
revision back log reported in NRC Operational Assessment Team (OAT)
Inspection Report (No. 50-333/82-24). The IIsensee's corrective
action was to reduce the back log using a plan reported in JAFP
Letter 82-0869 dated August 6, 1982.
However, as of May 3,1985,
the licensee has completed less than sixty percent of the drawings
scheduled for update in 1984.
If the present trend continues, the
licensee will not be able to meet the 1985 schedule. This back log
is further increased by the 1985 outage, which required more than
three thousand drawings to be revised. The White Plains Office
Support to the drawing revision efforts appeared to have lost the
initial level of attention. Additional corporate management
attention is required to meet the drawing revision goal.
Response: A meeting was held on site between Design & Analysis,
Project Engineering and the Site Technical Services Department to
address the noted problem. The drawing opdate procedure has been
modified to remove delays and to reduce .'ime to update a revised
drawing.
The attached list represents the status of the Drawing Update
Program as of 8/31/85
A review of all modifications by the Site
Technical Services Department shows that as of 9/16/85, approximately
82% of all installed modifications have completed drawing updates.
T
-
.
__
_
-
_-
_
-
'
^
.
-
- -
.
-;
-
,'
"
-
- -
ATTACHMENT ll
_
--
'
DRAWING UPDATE PROGRAM SCOPE
MODS WITH
DWG UPDATE
NO. OF
MODS SCHEDUL-
COMPLETED OR
DRAWINGS
NO. OF
ED FOR DWG.
VERIFIED AS
SCHEDULED
DRAWINGS
UPDATE
NOT INSTALLED
FOR UPDATE
COMPLETED
1983
130
130
1694
1694
1984
70
70
1086
1086
1985
35
25
724
480
TOTAL:
235
225
3504
3260
% Complete:
95%
% Complete:
93_t
ADDITIONAL WORK NOT IN ORIGINAL DRAWING UPDATE PROGRAM
MODS WITH
DWG UPDATE
NO. OF
MODS SCHEDUL-
COMPLETED OR
DRAWINGS
NO. OF
ED FOR DWG.
VERIFIED AS
SCHEDULED
DRAWINGS
UPDATE
NOT INSTALLED
FOR UPDATE
COMPLETED
1983
0
0
0
0
1984
27
27
82
82
1985
108
60
1439
754
TOTAL:
135
87
1521
836
MODS WITH
DWG. UPDATE
NO. OF
MODS SCHEDUL-
COMPLETED OR
DRAWINGS
NO. OF
ED FOR DWG.
VERIFIED AS
SCHEDULED
DRAWINGS
UPDATE
NOT INSTALLED
FOR UPDATE
~ COMPLETED
GRAND
TOTALS:
370
312
5025
4096
% Complete:
84%
% Complete:
81%
_
_
_
.
_ . .
-_
-._ _- _